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orgmode-to-gemini-blog/html/L’aventure Superphénix🔥. Superphénix… s’il est un réacteur… _ by Dragonfeu _ Medium.html
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L’aventure Superphénix🔥
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<p
id="d8b8"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Superphénix… s’il est un réacteur célèbre en
France, c’est bien lui. J’en parle souvent, avec
des regrets, mais aussi avec la fierté de vivre
dans le pays qui a développé un réacteur unique
au monde jamais égalé. En son temps, il était le
roi de tous les réacteurs, du haut de ses 1240
MW électriques, offrant un
<strong class="mb gv">réél</strong> potentiel
d’indépendance énergétique à la France.
</p>
<p
id="18fb"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Et si on en parlait, en prenant le temps, en
développant les concepts ?
</p>
<p
id="1408"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Pour celles &amp; ceux n’ayant pas un attrait
prononcé pour la technique, les premiers
paragraphes de cet article établiront une
présentation rapide de SPX. La suite ira plus en
profondeur, en s’appuyant sur les livres de Joël
Guidez, la monographie du CEA sur les RNR à
caloporteurs sodium, et des documents de l’IRSN
(sources à la fin de l’article).
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my mz">
<picture
><source
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 512px"
type="image/webp" />
<source
data-testid="og"
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 512px" />
<img
alt=""
class="bh ng nh c"
width="512"
height="341"
loading="eager"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Superphénix - centrale nucléaire de
Creys-Malville.
</figcaption>
</figure>
<h1
id="b7e2"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
Vous avez dit Superphénix ?
</h1>
<p
id="12c3"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Superphénix (désigné par le sigle SPX1 ou SPX)
est un réacteur nucléaire à neutrons rapides
(RNR) dont le caloporteur est le sodium (symbole
Na) sous forme liquide.
</p>
<p
id="c1a2"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv">Neutron </strong>: c’est
la particule élémentaire sans charge électrique
qui est responsable des fissions des éléments
fissiles (uranium 235 &amp; plutonium 239
principalement).
</p>
<p
id="09b2"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv">Neutron rapide</strong> :
c’est un neutron de forte énergie cinétique (Ec
= 0.5*masse*vitesse²). On utilise ce terme en
opposition aux neutrons thermiques (plus lents)
utilisés dans un réacteur à eau sous pression,
ceux que la France exploite actuellement. Un
neutron rapide n’a donc pas été ralenti dans un
modérateur. Un neutron rapide a une vitesse d’au
moins 13800 km/s, et un neutron thermique d’au
moins 2.2 km/s.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my op">
<picture
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="348"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Les neutrons rapides sont issus directement de
la fission. Ici c’est un réacteur avec un
modérateur, qui va venir ralentir les neutrons
rapides par une série de chocs. Les neutrons
lents ont une probabilité de fission avec les
noyaux d’U235 plus importante, et c’est ainsi
que la réaction en chaîne est maintenue.
</figcaption>
</figure>
<p
id="dd11"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv">Caloporteur : </strong
>vient du latin
<em class="ou">calor </em>pour<em class="ou">
</em
>chaleur. C’est donc le nom donné au fluide qui
circule pour extraire la chaleur. Dans un
réacteur nucléaire il peut y en avoir plusieurs.
Le plus connu est l’eau, qui sert à la fois de
fluide d’échange au circuit primaire, secondaire
et tertiaire.
</p>
<p
id="3e35"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Dans un réacteur à eau légère, on dit qu’on
utilise des neutrons thermiques, ou lents. Ils
ont perdu leur énergie cinétique par une
succession de chocs, et cela permet d’augmenter
sa “probabilité de fission” sur l’uranium 235.
Et donc, pourquoi les neutrons “rapides” ? Pour
aller fissionner plus facilement des atomes qui
ne le sont pas avec des neutrons thermiques ! La
courbe ci-dessous donne la “probabilité
d’interaction” selon l’énergie du neutron. En
rapide (1MeV donc), on voit une nette différence
entre la capture et la fission. Autrement dit,
dans le domaine rapide, probabilité de
fissionner est plus de 10 fois supérieure à
celle de l’absorption.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my ov">
<picture
><source
srcset="
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<img
alt=""
class="bh ng nh c"
width="583"
height="403"
loading="lazy"
role="presentation"
/></picture>
</div>
</figure>
<p
id="14b9"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Mais on peut aussi fertiliser les atomes
d’uranium 238 ! En le transformant en Pu239
justement, qui lui est fissile… On en reparle
juste en-dessous dans la partie “Surgénérateur
ou incinérateur ?”…
</p>
<p
id="43e7"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>Quelles sont les différences entre un REP
(réacteur actuel), et un RNR-Na?</strong
>
</p>
<p
id="dc1e"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Le changement principal intervient sur le
circuit primaire, comme détaillé ci-dessous. Un
échangeur intermédiaire, lui aussi en sodium,
est intercalé pour extraire la chaleur du cœur
et la transmettre aux générateurs de vapeur.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="ab cn cb ow">
<picture
><source
srcset="
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<img
alt=""
class="ng bh nh c"
width="700"
loading="lazy"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Différences REP/RNR
</figcaption>
</figure>
</div>
</div>
<div class="nf">
<div class="ab cb">
<div class="ox oy oz pa pb pc cf pd cg pe ci bh">
<div class="na nb nc nd ne ab ke">
<figure
class="le nf pf pg ph pi pj paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<picture
><source
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 594px"
type="image/webp" />
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data-testid="og"
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<img
alt=""
class="bh ng nh c"
width="594"
height="444"
loading="eager"
role="presentation"
/></picture>
</div>
</figure>
<figure
class="le nf pk pg ph pi pj paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<picture
><source
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 407px"
type="image/webp" />
<source
data-testid="og"
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 407px" />
<img
alt=""
class="bh ng nh c"
width="407"
height="567"
loading="eager"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du pl fj pm pn"
>
Schéma d’un REP sans aéroréfrigérant //
Schéma de SPX
</figcaption>
</figure>
</div>
</div>
</div>
</div>
<div class="ab cb">
<div class="ci bh fz ga gb gc">
<p
id="5c6e"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Les différences seront explicitées plus bas dans
la partie 3: “ La technologie RNR-Na”.
</p>
<h1
id="ea70"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
Surgénérateur, incinérateur, isogénérateur ?
</h1>
<p
id="9068"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Selon l’organisation du cœur et ce qu’on met
dans les assemblage combustible, plusieurs
possibilités s’offrent aux RNR-Na. Deux familles
nous intéressent. Les isotopes du plutonium et
les actinides mineurs.
</p>
<p
id="667a"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Les stocks de plutonium sont condamnés à
augmenter à court terme, ils augmentent même
dans les pays qui le recyclent (MOx), car les
réacteurs actuels n’en font pas disparaître
assez. Ce qu’on voit dans l’image ci-dessous est
la masse accumulée selon le temps en fonction du
cycle. Le cycle ouvert est l’option actuellement
poursuivie en France. Le scénario MIX
(valorisant les MOx) et RNR permettent
d’abaisser considérablement ces stocks.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my po">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/0*zTZA5eFDPhLudxao.jpg 640w,
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https://miro.medium.com/v2/resize:fit:1000/format:webp/0*zTZA5eFDPhLudxao.jpg 1000w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 500px"
type="image/webp" />
<source
data-testid="og"
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 500px" />
<img
alt=""
class="bh ng nh c"
width="500"
height="258"
loading="lazy"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Stocks de matière à valoriser
</figcaption>
</figure>
<h2
id="4227"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Incinérateur ?
</h2>
<p
id="995c"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
En enlevant l’enveloppe d’uranium 238 autour du
cœur, Superphénix pouvait devenir
sous-générateur : il pouvait consommer plus de
plutonium 239 qu’il n’en créait. Cela permettait
donc d’incinérer les déchets accumulés les plus
problématiques, et sans devoir miner un gramme
d’uranium naturel. Superphénix pouvait également
transmuter les actinides pour en faire des
déchets à vie courte. Le RNR-Na est
<strong class="mb gv"
>le seul concept mature</strong
>
capable de faire cela. Cette configuration a été
celle de SPX durant toute son existence.
</p>
<h2
id="7235"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Transmutateur ?
</h2>
<p
id="a665"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Pour les actinides, il est possible de remplacer
certaines alvéoles par des assemblages spéciaux
pour les faire fissionner, et réduire
drastiquement leur durée de vie (de plusieurs
centaines de milliers d’années à quelques
centaines).
</p>
<h2
id="984e"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
<strong class="al">Surgénérateur ?</strong>
</h2>
<p
id="023a"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
La capture neutronique sur l’uranium 238 à
l’intérieur du cœur ainsi que dans les
enveloppes en périphéries de cœur pouvait
produire plus de plutonium qu’il n’en
consommait. Ainsi, il pouvait régénérer son
propre stock de combustible à partir de matière
fertile. Le cœur de SPX, bien que capable de
passer en mode surgénération, n’a jamais été
fait, mais cela était bel et bien prévu par
l’exploitant.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my qe">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/0*-e6HZYGoOMeBXn22 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/0*-e6HZYGoOMeBXn22 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/0*-e6HZYGoOMeBXn22 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/0*-e6HZYGoOMeBXn22 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/0*-e6HZYGoOMeBXn22 828w,
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https://miro.medium.com/v2/resize:fit:1400/format:webp/0*-e6HZYGoOMeBXn22 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="700"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Fertilisation de l’U238 (<a
class="af qf"
href="https://www.orano.group/en/unpacking-nuclear/all-about-plutonium#:~:text=In%20this%20reaction%2C%20uranium%2D238,239%20transforms%20into%20plutonium%2D239."
rel="noopener ugc nofollow"
target="_blank"
>source</a
>)
</figcaption>
</figure>
<blockquote class="qg qh qi">
<p
id="af9d"
class="lz ma ou mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>Maintenant, on va un peu plus loin dans la
technique. Voici le plan :</strong
>
</p>
</blockquote>
<h1
id="be6d"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
1. Pourquoi faire Superphénix ?
</h1>
<h1
id="9bb1"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
2. L’histoire des RNR, du projet Manhattan
jusqu’à SPX2
</h1>
<h1
id="a07d"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
3. Pourquoi le sodium ?
</h1>
<h1
id="5aba"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
4. Principes de conception généraux
</h1>
<h1
id="cafc"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
5. Sûreté
</h1>
<h1
id="9b71"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
6. Les matériaux
</h1>
<h1
id="5127"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
7. Exploitation et bilan de SPX
</h1>
<h1
id="9654"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
8. La suite de SPX
</h1>
<h1
id="b785"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
9. Conclusion
</h1>
</div>
</div>
</div>
<div class="ab cb qj qk ql qm" role="separator">
<span class="qn by bm qo qp qq"></span
><span class="qn by bm qo qp qq"></span
><span class="qn by bm qo qp"></span>
</div>
<div class="gn go gp gq gr">
<div class="ab cb">
<div class="ci bh fz ga gb gc">
<h1
id="483a"
class="nm nn gu bf no np qr nr ns nt qs nv nw nx qt nz oa ob qu od oe of qv oh oi oj bk"
>
1. Pourquoi faire Superphénix ?
</h1>
<p
id="20fd"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
<em class="ou"
>Je reprendrai certains des mots de Georges
Vendryes (1920–2014), grand serviteur du
nucléaire français, dans “Superphénix pourquoi
?”, ouvrage dont je recommande la lecture, il
est accessible à toutes et tous.</em
>
</p>
<blockquote class="qw">
<p
id="53ce"
class="qx qy gu bf qz ra rb rc rd re rf mw du"
>
“Le premier pays qui mettra au point un
réacteur nucléaire surgénérateur en tirera un
avantage commercial décisif.” Enrico Fermi,
1945.
</p>
</blockquote>
<p
id="0ff9"
class="pw-post-body-paragraph lz ma gu mb b mc rg me mf mg rh mi mj mk ri mm mn mo rj mq mr ms rk mu mv mw gn bk"
>
<strong class="mb gv"
>Le grand-père de Superphénix,
Rapsodie</strong
>
</p>
<p
id="a16f"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
La France d’après 1945 se relève doucement et
créée en 1945 le Commissariat à l’Energie
Atomique, pour que la France soit souveraine sur
les technologies nucléaires militaires et
civiles. La recherche sur les neutrons rapides
en France part avec 10 ans de retard sur les
Etats-Unis (Clementine, EBR-1), l’URSS (BR2, 5
puis BR10) et la Grande-Bretagne (DFR). En 1958,
le CEA l’avant-projet sommaire de Rapsodie,
première “pile expérimentale à neutron rapides
refroidie au sodium” (on appellerait ça un
réacteur nucléaire aujourd’hui). L’objectif est
d’acquérir des données expérimentales pour
lancer plus tard un prototype dont on pourrait
convertir l’énergie du cœur. L’aventure des
neutrons rapides commence alors à Cadarache,
dans le Sud de la France. Sa construction
commença en 1962 et s’acheva en 1966, pour une
première divergence et l’atteinte de sa pleine
puissance (20MWth) en 1967. Il fut exploité
pendant 15 ans, et a ouvert la voie à Phénix.
</p>
<p
id="6fc8"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv">Son père, Phénix.</strong>
</p>
<p
id="b8c4"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
EDF et le CEA signent en 1969 un protocole
d’exploitation commun. Le réacteur fera 250MWe,
permettant de garder les dimensions
industrielles des groupes turbo-alternateurs
disponibles à l’époque. Début des travaux en
1968 et divergence en 1973, pleine puissance en
1974. Malgré quelques incidents propres à tout
prototype, le réacteur fonctionne 15 ans de
façon remarquable, et est le premier à utiliser
le plutonium qu’il a lui-même produit.<strong
class="mb gv"
>
Il atteint un taux de régénération de
1.16</strong
>
(16% de matière fissile en plus à la fin du
cycle par rapport au début).
<strong class="mb gv"
>Le concept de surgénérateur est validé
!</strong
>
</p>
<p
id="2717"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>La naissance de Superphénix.</strong
>
</p>
<p
id="2690"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Fin des années 70, après deux crises
pétrolières, et après avoir valider un concept
de RNR de grande puissance, la coopération
européenne pour l’échelon industriel se met en
place. Anglais, belges, hollandais, allemands,
italiens et français travaillent ensemble à la
construction de SPX. Le prototype de 1200MWe
commencé en 1976 qui atteint sa pleine puissance
en 1986. A l’époque EDF construisait les 900MWe
et concevait les futurs 1300MWe. L’objectif
était de se placer au même niveau que les
réacteurs de puissance.
</p>
<p
id="1b45"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>La volonté de fermer le cycle du combustible
français</strong
>
</p>
<p
id="497e"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Les qualités des RNR du point de vue du cycle
sont remarquables. Comme expliqué plus haut, les
deux configurations de cœur de type
<em class="ou">incinérateur </em>ou
<em class="ou">surgénérateur</em> donnent à SPX
un avantage considérable sur tous les autres
réacteurs à neutrons thermiques (qui constituent
au moins 95% des réacteurs actuels).
</p>
<p
id="5ae6"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">Plutonium</em>. Actuellement en
France, il est utilisé dans les REP sous forme
de MOx (“mix d’oxydes U-Pu”), mais il ne peut
être utilisé qu’une fois, sa qualité isotopique
se dégradant (c’est à dire que la proportion des
isotopes pairs, non fissiles, augmente). Le
multi-recyclage efficace ne peut avoir lieu que
grâce dans des RNR. Nous disposons aussi des
stocks de MOX usés (120 t/an), qui ne sont pas
valorisés actuellement malgré leur immense
potentiel énergétique.
</p>
<p
id="5375"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou"
>Autres ressources valorisables.</em
>
L’uranium de retraitement appauvri (800 t/an) et
l’uranium de retraitement réutilisé (140 t/an),
sont également actuellement
<strong class="mb gv"
>très peu valorisés, alors qu’ils pourraient
servir de combustible dans un parc de
réacteurs rapides</strong
>. Enfin, mais cela est encore à confirmer, il
est possible sur le papier de convertir les
actinides mineurs par transmutation ce qui
diminuerait encore la quantité et la toxicité de
ces déchets ultimes. Les déchets les plus
complexes à gérer sont actuellement produits par
le parc français à hauteur d’environ 40 t/an, ce
qui est ridicule au vue de l’énergie produite
mais reste néanmoins un enjeu de gestion
(stratégie d’entreposage et de refroidissement).
Cela sera détaillé plus loin.
</p>
</div>
</div>
</div>
<div class="ab cb qj qk ql qm" role="separator">
<span class="qn by bm qo qp qq"></span
><span class="qn by bm qo qp qq"></span
><span class="qn by bm qo qp"></span>
</div>
<div class="gn go gp gq gr">
<div class="ab cb">
<div class="ci bh fz ga gb gc">
<h1
id="886a"
class="nm nn gu bf no np qr nr ns nt qs nv nw nx qt nz oa ob qu od oe of qv oh oi oj bk"
>
2. L’histoire des RNR, du projet Manhattan
jusqu’à SPX2
</h1>
<p
id="7758"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
C’est important de comprendre la génèse de
l’idée derrière le RNR. Ce concept est en
réalité apparu dans les esprits des physiciens à
peu près au même moment que celui des réacteurs
à modérateurs.
</p>
<p
id="5165"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Enrico Fermi, futur prix Nobel de physique, qui
travaillait alors sur la pile de Chicago, a été
le premier à étudier les neutrons rapides. Il a
remarqué que les neutrons lents causaient plus
fréquemment des fissions que les neutrons
rapides, découvrant alors le principe de section
efficace. Le projet Manhattan achevé, la
recherche sur les applications de la fission
nucléaire allait bientôt devenir un enjeu majeur
pour cette deuxième moitié du XXe siècle.
</p>
<blockquote class="qw">
<p
id="785a"
class="qx qy gu bf qz ra rb rc rd re rf mw du"
>
“L’énergie nucléaire est une sacrée façon de
faire bouillir de l’eau“, Albert Einstein
(1879–1955).
</p>
</blockquote>
<p
id="add3"
class="pw-post-body-paragraph lz ma gu mb b mc rg me mf mg rh mi mj mk ri mm mn mo rj mq mr ms rk mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1935</span
>
Frédéric Joliot-Curie prononce ces mots en
conclusion de sa conférence qu’il donne après la
réception de son prix Nobel de chimie: “Nous
sommes en droit de penser que les chercheurs,
construisant ou brisant les atomes à volonté,
sauront réaliser des transmutations à caractère
explosif, véritables réactions chimiques à
chaînes. Si de telles transformations arrivent à
se propager dans la matière, on peut concevoir
l’énorme libération d’énergie utilisable qui
aura lieu”.
</p>
<p
id="e5ed"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1942</span
>
La pile de Chicago est en place et le 2 décembre
1942 à 15h25, la première réaction en chaîne
artificielle auto-entretenue débute.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my ru">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/0*iPdFAaDGtnVDmARR.jpg 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/0*iPdFAaDGtnVDmARR.jpg 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/0*iPdFAaDGtnVDmARR.jpg 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/0*iPdFAaDGtnVDmARR.jpg 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/0*iPdFAaDGtnVDmARR.jpg 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/0*iPdFAaDGtnVDmARR.jpg 1100w,
https://miro.medium.com/v2/resize:fit:1280/format:webp/0*iPdFAaDGtnVDmARR.jpg 1280w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 640px"
type="image/webp" />
<source
data-testid="og"
srcset="
https://miro.medium.com/v2/resize:fit:640/0*iPdFAaDGtnVDmARR.jpg 640w,
https://miro.medium.com/v2/resize:fit:720/0*iPdFAaDGtnVDmARR.jpg 720w,
https://miro.medium.com/v2/resize:fit:750/0*iPdFAaDGtnVDmARR.jpg 750w,
https://miro.medium.com/v2/resize:fit:786/0*iPdFAaDGtnVDmARR.jpg 786w,
https://miro.medium.com/v2/resize:fit:828/0*iPdFAaDGtnVDmARR.jpg 828w,
https://miro.medium.com/v2/resize:fit:1100/0*iPdFAaDGtnVDmARR.jpg 1100w,
https://miro.medium.com/v2/resize:fit:1280/0*iPdFAaDGtnVDmARR.jpg 1280w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 640px" />
<img
alt=""
class="bh ng nh c"
width="640"
height="285"
loading="lazy"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Dessin de la pile CP-1 à Chicago
</figcaption>
</figure>
<p
id="ee48"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1945</span
>Enrico Fermi propose le concept de réacteur
surgénérateur. Un réacteur produisant plus de
matière fissile qu’il n’en consomme.
</p>
<p
id="8c1f"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1946</span
>Le premier réacteur nucléaire à neutrons
rapides,
<a
class="af qf"
href="https://fr.wikipedia.org/wiki/Clementine_(r%C3%A9acteur)"
rel="noopener ugc nofollow"
target="_blank"
>Clementine</a
>, diverge. Il a un caloporteur au mercure. Son
objectif était d’étudirr les propriétés
nucléaires de plusieurs matériaux à la suite du
succès du projet Manhattan. Ce réacteur a servi
à de nombreuses expériences, comme prouver la
possibilité de faire un surgénérateur civil, ou
encore mesurer les sections efficaces de
plusieurs isotopes.
</p>
<p
id="f48f"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1951</span
>Le premier réacteur nucléaire électrogène,
EBR-I pour
<a
class="af qf"
href="https://fr.wikipedia.org/wiki/Experimental_Breeder_Reactor_I"
rel="noopener ugc nofollow"
target="_blank"
><em class="ou"
>Experimental Breeder Reactor I</em
></a
>, produit assez de puissance pour allumer 4
ampoules. Son caloporteur est un eutectique
sodium-potassium (Na-K).
</p>
<figure class="na nb nc nd ne nf">
<div class="rv rw l fj">
<div class="rx ry l"></div>
</div>
</figure>
<p
id="6a46"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1956</span
>Création du consortium européen EUROCHEMIC,
première agence européenne de coopération
technique nucléaire.
</p>
<p
id="8b67"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1958</span
>Début du fonctionnement de l’unité de
retraitement du plutonium UP1 à Marcoule.
</p>
<p
id="1d1f"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1962</span
>Construction de Rapsodie, premier RNR-Na en
France, critique en 1967. 20MWth. Fonctionnera
jusqu’en 1983.
</p>
<p
id="02db"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1968</span
>Construction de phénix par le CEA et EDF.
560MWth. Il fonctionnera jusqu’en 2010.
</p>
<p
id="46e3"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1976</span
>Construction de Superphénix dit SPX, 1200MWe.
L’échelon industriel des RNR-Na, plus gros RNR
jamais construit à ce jour. Pleine puissance en
1986, après seulement 10 ans.
</p>
<p
id="7eb4"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk rl"
>
<span class="l rm rn ro bo rp rq rr rs rt fj"
>1992</span
>Le redémarrage de Superphénix est soumis à la
réalisation préalable d’une étude (Rapport
Curien) sur la contribution que pourrait
apporter Superphénix à l’incinération des
déchets radioactifs. Cette étude confirme
l’intérêt de SPX pour ce sujet, et le
redémarrage est autorisé le 17 décembre 1992.
</p>
</div>
</div>
</div>
<div class="ab cb qj qk ql qm" role="separator">
<span class="qn by bm qo qp qq"></span
><span class="qn by bm qo qp qq"></span
><span class="qn by bm qo qp"></span>
</div>
<div class="gn go gp gq gr">
<div class="ab cb">
<div class="ci bh fz ga gb gc">
<h1
id="a201"
class="nm nn gu bf no np qr nr ns nt qs nv nw nx qt nz oa ob qu od oe of qv oh oi oj bk"
>
3. Pourquoi le sodium ?
</h1>
<p
id="fc1a"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Les RNR ont autant de design que de
caloporteurs. Certains choisissent des métaux
liquides purs (Na, Pb, Hg), d’autres des
eutectiques (Pb-Bi, Na-K), ou encore le gaz
(He). Certains choisissent aussi l’option des
sels (chlorure ou fluorure). Le choix du sodium
présente un certain nombre d’avantages et la
famille de RNR ayant le plus de retour
d’expérience dans le monde est de loin celle du
sodium.
</p>
<p
id="d8ed"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Un certain nombre de critères doivent
s’appliquer au caloporteur d’un RNR. Le premier,
assez logiquement, est sa transparence aux
neutrons, afin de modérer peu. On cherche donc
un matériau faiblement absorbant et à faible
pouvoir de ralentissement, ce qui exclut de fait
la plupart des matériaux légers.
</p>
<p
id="de83"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Ensuite, on veut un caloporteur efficace, il
doit donc avoir une forte capacité calorifique
et une bonne conductivité thermique. Son
écoulement en cœur doit être excellent et ne pas
demander un effort trop important aux pompes
primaires, il doit donc être peu visqueux.
</p>
<p
id="9dee"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Ensuite, il doit être capable d’encaisser les
transitoires en restant monophasique liquide, il
faut éviter qu’il se solidifie et qu’il
s’évapore.
</p>
<p
id="0b13"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Le caloporteur doit être aussi pur que possible
pour éviter les produits d’activation dans le
circuit, ce qui compliquerait la maintenance. On
veut également éviter qu’il soit corrosif pour
les structures internes.
</p>
<p
id="4fb9"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Enfin, il doit être disponible à bas coût, en
quantité industrielle, et le plus pur possible.
</p>
<p
id="3c32"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Bilan pour le sodium : ses températures de
fusion (97,8°C) et d’ébullition (883°C)
permettent, à 500°C, une utilisation à la
pression atmosphérique. Il a une très bonne
conductibilité thermique (100 fois celle de
l’eau). Il absorbe très peu les neutrons et a
une faible capacité à les ralentir (mais cette
composante n’est pas nulle pour autant, nous le
verrons dans la partie sûreté). Le sodium ne
s’active pas non plus est est peu corrosif. Il
est excellent d’un point de vue neutronique et
thermohydraulique mais mauvais sur la
physico-chimie du fait de la réaction Na-H2O
très exothermique et de son inflammation au
contact de l’air. Le sodium n’est pas cher et
est adapté à l’usage industriel.
</p>
</div>
</div>
</div>
<div class="ab cb qj qk ql qm" role="separator">
<span class="qn by bm qo qp qq"></span
><span class="qn by bm qo qp qq"></span
><span class="qn by bm qo qp"></span>
</div>
<div class="gn go gp gq gr">
<div class="ab cb">
<div class="ci bh fz ga gb gc">
<h1
id="5051"
class="nm nn gu bf no np qr nr ns nt qs nv nw nx qt nz oa ob qu od oe of qv oh oi oj bk"
>
<strong class="al"
>4. Principes de conception généraux</strong
>
</h1>
<h2
id="ed07"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
<strong class="al">Neutronique du cœur</strong>
</h2>
<p
id="6fb6"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
On utilise communément une unité d’énergie
appelée
<a
class="af qf"
href="https://fr.wikipedia.org/wiki/%C3%89lectronvolt"
rel="noopener ugc nofollow"
target="_blank"
>électron-volt</a
>
pour l’énergie cinétique des neutrons.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my rz">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/0*S0LU7Ni1zxO-uopT 640w,
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https://miro.medium.com/v2/resize:fit:750/format:webp/0*S0LU7Ni1zxO-uopT 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/0*S0LU7Ni1zxO-uopT 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/0*S0LU7Ni1zxO-uopT 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/0*S0LU7Ni1zxO-uopT 1100w,
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"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 602px"
type="image/webp" />
<source
data-testid="og"
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 602px" />
<img
alt=""
class="bh ng nh c"
width="602"
height="298"
loading="lazy"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Les différentes catégories de neutrons.
</figcaption>
</figure>
<p
id="9ab5"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Superphénix est un réacteur à neutrons rapides
(RNR), ce qui signifie que sa population de
neutron sera (très majoritairement) dans le
“spectre” rapide, de 10⁵eV à 2*10⁷eV, comme le
montre la courbe orange ci-dessous.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my sa">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/1*tq-ETHC-CEocwEuGIPxoAg.png 640w,
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 681px"
type="image/webp" />
<source
data-testid="og"
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 681px" />
<img
alt=""
class="bh ng nh c"
width="681"
height="613"
loading="lazy"
role="presentation"
/></picture>
</div>
</figure>
<h2
id="34c9"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Conception générale du cœur
</h2>
<p
id="600f"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
<em class="ou"
>Coefficient de contre réaction. Parler de la
CFV non échelonable.</em
>
</p>
<p
id="05f9"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">à finir</em>
</p>
<h2
id="d44f"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Combustible
</h2>
<p
id="ffb7"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Le combustible a une géométrie hexagonale
(carrée en REP), et est disposé dans des
“aiguilles ” (“crayons” en REP). La géométrie en
aiguille est choisie pour sa compacité, un
combustible RNR-Na doit avoir au moins 15% de
plutonium.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sb">
<picture
><source
srcset="
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type="image/webp" />
<source
data-testid="og"
srcset="
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<img
alt=""
class="bh ng nh c"
width="700"
height="774"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
AC pour SPX
</figcaption>
</figure>
<h2
id="9284"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
L’échangeur intermédiaire
</h2>
<p
id="1125"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Dans un RNR-Na, il y a un échangeur
supplémentaire, intercalé entre le circuit
primaire et le circuit turbine. Pourquoi ?
</p>
<ol class="">
<li
id="9018"
class="lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw sc sd se bk"
>
On veut éviter le contact entre l’eau du
circuit turbine et le sodium primaire
(réaction très exothermique, boom)…
</li>
<li
id="4d99"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw sc sd se bk"
>
En cas de réaction sodium-eau, on évite
d’avoir un sodium activé (radioactif).
</li>
</ol>
<p
id="0c26"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Deux concepts d’organisation de ce circuit
intermédiaire sont proposés. La différence
repose sur la localisation de l’échangeur
intermédiaire, dans la cuve (<em class="ou"
>concept intégré</em
>) ou en dehors (<em class="ou"
>concept à boucles</em
>, comme sur REP). Le caloporteur utilisé dans
cet échangeur est également du sodium, après
avoir écarté l’option de l’eutectique Pb-Bi. Des
concepts récents (<a
class="af qf"
href="https://www.hexana.fr/"
rel="noopener ugc nofollow"
target="_blank"
>Hexana</a
>) proposent d’utiliser un sel fondu.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sk">
<picture
><source
srcset="
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<img
alt=""
class="bh ng nh c"
width="700"
height="356"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Concepts d’organisation des circuits
intermédiaires d’un RNR-Na
</figcaption>
</figure>
<h2
id="3877"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Systèmes de conversion
</h2>
<p
id="d405"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Les générateurs de vapeur (GV) sont hélicoïdaux
sur SPX, contrairement à ceux des REP, et encore
différents des GV en épingle de Phénix.
L’avantage de cette géométrie est qu’elle
présente une grande longueur (80m). Les GV de
SPX sont conçus en un seul morceau, comme sur
REP, moins chers mais plus durs à changer. Les
tubes sont en Alliage 800. Les caractéristiques
sont détaillées ci-dessous. Le GV avait beau
être le premier du genre, aucun incident majeur
n’a été déclaré pendant ses 748 jours
d’opérations.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my sl">
<picture
><source
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<img
alt=""
class="bh ng nh c"
width="433"
height="764"
loading="lazy"
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/></picture>
</div>
</figure>
<h2
id="0f75"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
La cuve
</h2>
<p
id="b7c6"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
C’est assez particulier sur SPX, il y a deux
cuve. Une cuve dans une autre. La cuve la plus
intérieure contient l’ensemble du circuit
primaire, et la cuve de sécurité qui l’entoure
permet de contrôler les fuites sodium et de
valoriser la convection naturelle de ce dernier,
et donc en évacuant la chaleur résiduelle, ce
qui permet d’éviter l’évaporation du sodium. Sur
Phénix, la faible puissance relative à la
surface de cuve permettait de refroidir
uniquement par rayonnement de la face externe de
la cuve.
</p>
<p
id="e88a"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Le choix fait sur SPX est de prendre la cuve
principale, la dalle supérieure prend la masse.
Un schéma pour bien comprendre.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sm">
<picture
><source
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type="image/webp" />
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<img
alt=""
class="bh ng nh c"
width="700"
height="469"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Sur ce schéma, en gris clair la cuve
principale, en forme d’entonnoir. La cuve de
sécurité englobe les pompes primaires.
(source:
<a
class="af qf"
href="https://www.isere.fr/sites/default/files/presentation-edf-cli-publique-de-creys-malville-08112022-vedef.pdf"
rel="noopener ugc nofollow"
target="_blank"
>EDF</a
>)
</figcaption>
</figure>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sn">
<picture
><source
srcset="
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https://miro.medium.com/v2/resize:fit:750/format:webp/0*5M_C2LxfKK_OKLYf 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/0*5M_C2LxfKK_OKLYf 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/0*5M_C2LxfKK_OKLYf 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/0*5M_C2LxfKK_OKLYf 1100w,
https://miro.medium.com/v2/resize:fit:1400/format:webp/0*5M_C2LxfKK_OKLYf 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="525"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
La cuve de SPX, de 21m de diamètre.
</figcaption>
</figure>
<h2
id="4f73"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Les pompes primaires
</h2>
<p
id="dd73"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Elles sont toutes mécaniques, et non pas
électromagnétiques (réacteurs du futur). Ces
pompes sont au nombre de quatre, d’une hauteur
de 15 m, d’un diamètre maximum 2,5 m pour une
masse totale sans moteur et avec protection
biologique de 120 tonnes. Leur débit atteint
presque 4.8m3/s.
</p>
<p
id="0158"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Chose à noter, la pompe étant suspendue par en
haut, les dilatations thermiques à l’entrée sont
importantes. Ainsi la pompe est supportée à sa
partie supérieure par un anneau flexible
permettant la libre inclinaison de la pompe sous
l’action des déplacements différentiels.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my so">
<picture
><source
srcset="
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type="image/webp" />
<source
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<img
alt=""
class="bh ng nh c"
width="670"
height="576"
loading="lazy"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
<a
class="af qf"
href="https://www.shf-lhb.org/articles/lhb/pdf/1977/05/lhb1977054.pdf"
rel="noopener ugc nofollow"
target="_blank"
>source</a
>
</figcaption>
</figure>
<h2
id="6d72"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Le bouchon couvercle cœur (BCC)
</h2>
<p
id="427a"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
On parle ici de la pièce amovible positionnée en
haut du cœur et reposant sur la dalle de
maintien.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sp">
<picture
><source
srcset="
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type="image/webp" />
<source
data-testid="og"
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<img
alt=""
class="bh ng nh c"
width="700"
height="492"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
</figure>
<p
id="f1f1"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
C’est une pièce multifonction. Il sert à fermer
le circuit primaire par le haut, assurant
l’étanchéité. Comme sur un REP, le BCC supporte
et positionne les mécanismes de commande des
barres et l’instrumentation de surveillance du
cœur. Il a aussi un rôle de protection
biologique et thermique. Par rapport à un REP,
le BCC a aussi une fonction hydraulique, il
dévie les jets de sodium à la sortie du cœur.
</p>
<h1
id="0a60"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
5. Sûreté
</h1>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sq">
<picture
><source
srcset="
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type="image/webp" />
<source
data-testid="og"
srcset="
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<img
alt=""
class="bh ng nh c"
width="700"
height="394"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
</figure>
<h2
id="9956"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
<strong class="al"
>Maitrise de la réactivité</strong
>
</h2>
<p
id="cadc"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Déjà, le réacteur dispose de grappes d’arrêt
pour stopper la réaction en chaîne, elles sont
placées en haut (cf. schéma ci-dessous). L’<a
class="af qf"
href="https://fr.wikipedia.org/wiki/Empoisonnement_au_x%C3%A9non"
rel="noopener ugc nofollow"
target="_blank"
>effet Xénon</a
>
n’est pas présent, simplifiant le contrôle de la
réactivité du cœur. Le centre du cœur, là où il
est le plus chaud, induit des variations de
densité du sodium, contribuant à des insertions
ponctuelles de réactivité. L’objectif est de se
prémunir en concevant un cœur CFV (faible
vidange) comme le projet ASTRID. L’effet est
d’autant plus fort que le cœur est grand.
</p>
<h2
id="8877"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
<strong class="al"
>Evacuation de la puissance</strong
>
</h2>
<p
id="b06d"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Le sodium a une plus grande marge à l’ébullition
que l’eau par rapport au fonctionnement normal.
L’
<a
class="af qf"
href="https://fr.wikipedia.org/wiki/Inertie_thermique"
rel="noopener ugc nofollow"
target="_blank"
>inertie thermique</a
>
du sodium ( résistance au changement température
lors d’un transitoire). Des systèmes diversifiés
sont mis en place pour évacuer la puissance
résiduelle, dont des échangeurs sodium-air. Sur
SPX, le DRACS est le BPR sont passifs à 4
boucles. Le RVACS est actif à deux boucles. Il
n’y a pas de SGOSHDR sur SPX.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sr">
<picture
><source
srcset="
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"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
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https://miro.medium.com/v2/resize:fit:786/1*J6xpVMVQnIY33Jb1wIBeLQ.png 786w,
https://miro.medium.com/v2/resize:fit:828/1*J6xpVMVQnIY33Jb1wIBeLQ.png 828w,
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="473"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
</figure>
<h2
id="1f26"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
<strong class="al"
>Maitrise du confinement</strong
>
</h2>
<p
id="3937"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
<em class="ou"
>Première barrière (gaine combustible)</em
>
: la conductivité thermique élevée du sodium
(x70 par rapport à l’eau) assure un coefficient
d’échange important entre les gaines et le
sodium. Concernant les ruptures de gaine, elles
sont de deux types,
<em class="ou">ouverte </em>ou
<em class="ou">gazeuse</em>. Les RNR français
sont équipés du système DND (Détection de
Neutrons Différés) pour détecter les ruptures
ouvertes de gaine. L’assemblage défectueux est
ensuite identifié et retiré du cœur (on
s’interdit de fonctionner en gaines percées).
Dans le cas des ruptures par rejet de gaz de
fission, des rejets peuvent alors avoir lieu par
les soupapes de protection du circuit d’argon du
ciel de pile
</p>
<p
id="312d"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">La deuxième barrière</em> est
assez complexe à définir sur RNR-Na, on va donc
regarder seulement le concept intégré ici (type
SPX).
</p>
<ul class="">
<li
id="9a88"
class="lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw ss sd se bk"
>
cuve principale du réacteur (21m de diamètre),
</li>
<li
id="7562"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
cuve de sécurité, cette dernière étant prévue
pour collecter le sodium primaire en cas de la
fuite de la cuve principale (22.5m de
diamètre),
</li>
<li
id="2963"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
fermeture supérieure du réacteur,
</li>
<li
id="bab8"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
circuits auxiliaires véhiculant du sodium
primaire ou du gaz de couverture (argon) hors
du circuit primaire,
</li>
<li
id="008b"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
tubes des échangeurs intermédiaires (EI)
séparant le sodium primaire du sodium
intermédiaire,
</li>
<li
id="b3bc"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
tubes des échangeurs des circuits d’évacuation
de la puissance résiduelle immergés dans le
circuit primaire.
</li>
</ul>
<p
id="ad44"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
En résumé, tout ce qui constitue la cuve et sa
partie supérieure, plus les traversées. Cette
barrière
<strong class="mb gv"
>n’est pas étanche. </strong
>Il existe des fuites d’argon au niveau de la
fermeture supérieure par l’ouverture des
soupapes pour réguler la pression du “ciel de
pile”. Ces fuites sont contrôlées et mesurées
régulièrement.
</p>
<p
id="95cf"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou"
>La troisième barrière (bâtiment en béton très
résistant</em
>) la très faible pression primaire simplifie
grandement les problématiques de fuite et de
tenue de l’enceinte de confinement. En revanche,
la réaction sodium-eau est à surveiller, ne
serait-ce qu’avec l’humidité ambiante. Certains
designs proposent de changer l’eau par du
<a
class="af qf"
href="https://fr.wikipedia.org/wiki/Dioxyde_de_carbone_supercritique"
rel="noopener ugc nofollow"
target="_blank"
>CO2 supercritique</a
>.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my op">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/0*unhnYoEL7Gc-iUsW.jpg 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/0*unhnYoEL7Gc-iUsW.jpg 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/0*unhnYoEL7Gc-iUsW.jpg 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/0*unhnYoEL7Gc-iUsW.jpg 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/0*unhnYoEL7Gc-iUsW.jpg 828w,
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"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="467"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Troisième barrière qui est la plus grande
jamais construite.
</figcaption>
</figure>
<h2
id="e8e2"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
La sûreté de manutention du combustible neuf et
usé
</h2>
<p
id="9219"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
<em class="ou">A finir</em>
</p>
<h2
id="512d"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
<strong class="al"
>La gestion des accidents graves</strong
>
</h2>
<p
id="6b63"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Concernant les accidents graves, les normes à
l’époque de Phénix n’imposaient pas de système
de mitigation. SPX avait quand à lui un
récupérateur à débris de corium dans sa cuve. On
l’appelait le cendrier, il était originellement
conçu pour résister à la fusion complète de 7
assemblages, la fusion totale étant jugée trop
improbable en raison des caractéristiques de
sûreté du cœur.
</p>
<h1
id="b17b"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
6. Cycle combustible
</h1>
<blockquote class="qg qh qi">
<p
id="b3dd"
class="lz ma ou mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Cette partie est la plus important pour
comprendre l’intérêt des RNR-Na dans une
optique de gestion durables des matières
radioactives françaises. La France est assise
sur une mine d’or qui ne demande qu’à être
exploité, à la différence notable que, cette
fois, l’or est déjà miné et ne demande qu’à
être valorisé.
</p>
</blockquote>
<h2
id="28b0"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Complémentarité REP-RNR
</h2>
<p
id="18ea"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Il est important de comprendre que les RNR se
positionnent comme l’étape suivant celle du
déploiement de REP. Le plutonium généré par les
irradiations en REP permet de démarrer des RNR.
Le MOx neuf (voire usé) est exploitable en coeur
rapide. C’est un point clé car cela permet de se
baser sur un cycle existant, ce qui donne au
RNR-Na un avantage considérable sur d’autres
technologies de 4e génération tels que les
réacteurs à haute température (<a
class="af qf"
href="https://laradioactivite.com/articles/energie_nucleaire/reacteursahautestemperatures"
rel="noopener ugc nofollow"
target="_blank"
>HTR</a
>) à combustible
<a
class="af qf"
href="https://www.discoverthegreentech.com/nucleaire/combustibles/triso/"
rel="noopener ugc nofollow"
target="_blank"
>TRISO </a
>ou les réacteurs à
<a
class="af qf"
href="https://medium.com/p/69f2170689ca/edit"
rel="noopener"
>sels fondus</a
>
(sel chlorure ou fluorure)
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my st">
<picture
><source
srcset="
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https://miro.medium.com/v2/resize:fit:720/format:webp/1*leO_xZlNWAHRpNrBBqGMOg.png 720w,
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"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
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<img
alt=""
class="bh ng nh c"
width="700"
height="433"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Source [1] p.158
</figcaption>
</figure>
<p
id="0ba7"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
En l’état actuel du cycle français, le parc
produit environ 10 tonnes de Pu par an. Les REP
viennent donc se placer comme l’étape
préliminaire (et indispensable) à
l’établissement d’une filière rapide qui a
besoin de plutonium pour démarrer ses premiers
cœurs. L’objectif à très long terme (plusieurs
décennies) est la surgénération, qui permet
ensuite à la filière de s’autoalimenter. Ainsi
il est nécessaire de maintenir la filière REP
pour accompagner les premiers RNR.
</p>
<h2
id="2504"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Retraitement du combustible
</h2>
<p
id="5ad9"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
<em class="ou">A finir</em>
</p>
<h2
id="a6dd"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
Transmutation des actinides mineurs
</h2>
<p
id="161c"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Déjà, de quels isotopes parle-t-on ? Dans
l’ordre d’importance, l’Américium (Am 241, Am
243), le Curium (Cm 244, Cm 245) et le Neptunium
(Np 237).
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my su">
<picture
><source
srcset="
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sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
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data-testid="og"
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<img
alt=""
class="bh ng nh c"
width="700"
height="353"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Combustible usé de REP-UOx
</figcaption>
</figure>
<p
id="9b25"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
L’objectif est double, obtenir des colis moins
toxiques…et beaucoup moins chauds ! Je ne vous
dirai pas que les déchets ne seront plus un
problème, mais la transmutation des AM ouvre la
voie à des modes de gestion beaucoup plus
simples. De plus, cela permettrait d’utiliser
CIGEO encore mieux, du fait de la possibilité
d’augmentation de concentration de matière dans
les alvéoles, la chaleur résiduelle étant moins
élevée ! Ci-dessous, les contributions des AM à
la radiotoxicité des colis et à leur chaleur.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sv">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/1*t8oKQWCaNjids5IOfh9IpQ.png 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/1*t8oKQWCaNjids5IOfh9IpQ.png 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/1*t8oKQWCaNjids5IOfh9IpQ.png 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/1*t8oKQWCaNjids5IOfh9IpQ.png 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/1*t8oKQWCaNjids5IOfh9IpQ.png 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/1*t8oKQWCaNjids5IOfh9IpQ.png 1100w,
https://miro.medium.com/v2/resize:fit:1400/format:webp/1*t8oKQWCaNjids5IOfh9IpQ.png 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
https://miro.medium.com/v2/resize:fit:640/1*t8oKQWCaNjids5IOfh9IpQ.png 640w,
https://miro.medium.com/v2/resize:fit:720/1*t8oKQWCaNjids5IOfh9IpQ.png 720w,
https://miro.medium.com/v2/resize:fit:750/1*t8oKQWCaNjids5IOfh9IpQ.png 750w,
https://miro.medium.com/v2/resize:fit:786/1*t8oKQWCaNjids5IOfh9IpQ.png 786w,
https://miro.medium.com/v2/resize:fit:828/1*t8oKQWCaNjids5IOfh9IpQ.png 828w,
https://miro.medium.com/v2/resize:fit:1100/1*t8oKQWCaNjids5IOfh9IpQ.png 1100w,
https://miro.medium.com/v2/resize:fit:1400/1*t8oKQWCaNjids5IOfh9IpQ.png 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="434"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Convertir les actinides mineurs en énergie
permettrait de diminuer leur radiotoxicité.
(cf. [1] p.171)
</figcaption>
</figure>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sw">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/1*1XmAatwfBsPURmZV7K2Wnw.png 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/1*1XmAatwfBsPURmZV7K2Wnw.png 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/1*1XmAatwfBsPURmZV7K2Wnw.png 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/1*1XmAatwfBsPURmZV7K2Wnw.png 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/1*1XmAatwfBsPURmZV7K2Wnw.png 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/1*1XmAatwfBsPURmZV7K2Wnw.png 1100w,
https://miro.medium.com/v2/resize:fit:1400/format:webp/1*1XmAatwfBsPURmZV7K2Wnw.png 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
https://miro.medium.com/v2/resize:fit:640/1*1XmAatwfBsPURmZV7K2Wnw.png 640w,
https://miro.medium.com/v2/resize:fit:720/1*1XmAatwfBsPURmZV7K2Wnw.png 720w,
https://miro.medium.com/v2/resize:fit:750/1*1XmAatwfBsPURmZV7K2Wnw.png 750w,
https://miro.medium.com/v2/resize:fit:786/1*1XmAatwfBsPURmZV7K2Wnw.png 786w,
https://miro.medium.com/v2/resize:fit:828/1*1XmAatwfBsPURmZV7K2Wnw.png 828w,
https://miro.medium.com/v2/resize:fit:1100/1*1XmAatwfBsPURmZV7K2Wnw.png 1100w,
https://miro.medium.com/v2/resize:fit:1400/1*1XmAatwfBsPURmZV7K2Wnw.png 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="446"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Mais cela ferait aussi des colis moins chauds
à gérer. (cf. [1] p.171)
</figcaption>
</figure>
<p
id="cd0d"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Les processus chimiques impliqués dans le
retraitement et l’extraction des actinides
mineurs dépassent mes compétences, mais les
personnes intéressées peuvent toujours aller
lire la monographie CEA sur la séparation des
actinides des combustibles usés (disponible
<a
class="af qf"
href="https://www.cea.fr/multimedia/Documents/publications/monographie-nucleaire/CEA_Monographie6_Traitement-recyclage-combustible-nucleaire-use_2008_Fr.pdf"
rel="noopener ugc nofollow"
target="_blank"
>ici</a
>). C’est un sujet passionnant qui mériterait un
article entier, mais n’étant pas chimiste je ne
m’y risquerai pas.
</p>
<p
id="565c"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
En supposant une extraction efficace dans le
combustible de ces AM, on peut maintenant
regarder les potentiels usages en RNR. Déjà, la
neutronique du RNR est plus favorable à la
transmutation des AM:
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my sx">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/1*K2wBrjRhDJvf0mzf2eO-nQ.png 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/1*K2wBrjRhDJvf0mzf2eO-nQ.png 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/1*K2wBrjRhDJvf0mzf2eO-nQ.png 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/1*K2wBrjRhDJvf0mzf2eO-nQ.png 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/1*K2wBrjRhDJvf0mzf2eO-nQ.png 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/1*K2wBrjRhDJvf0mzf2eO-nQ.png 1100w,
https://miro.medium.com/v2/resize:fit:1128/format:webp/1*K2wBrjRhDJvf0mzf2eO-nQ.png 1128w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 564px"
type="image/webp" />
<source
data-testid="og"
srcset="
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https://miro.medium.com/v2/resize:fit:750/1*K2wBrjRhDJvf0mzf2eO-nQ.png 750w,
https://miro.medium.com/v2/resize:fit:786/1*K2wBrjRhDJvf0mzf2eO-nQ.png 786w,
https://miro.medium.com/v2/resize:fit:828/1*K2wBrjRhDJvf0mzf2eO-nQ.png 828w,
https://miro.medium.com/v2/resize:fit:1100/1*K2wBrjRhDJvf0mzf2eO-nQ.png 1100w,
https://miro.medium.com/v2/resize:fit:1128/1*K2wBrjRhDJvf0mzf2eO-nQ.png 1128w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 564px" />
<img
alt=""
class="bh ng nh c"
width="564"
height="296"
loading="lazy"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
A comprendre ainsi: “Le Neptunium 237 a 30
fois plus de chance d’être capturé que de
fissionner en REP-MOx. Cela passe à 5.3 en
RNR-MOx”.
</figcaption>
</figure>
<h1
id="b2cd"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
6. Les matériaux
</h1>
<h2
id="c9e3"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
6.1 Les matériaux du combustible
</h2>
<p
id="4c92"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Les matériaux structurels sont en acier
inoxydable austénitique. Le combustible est une
poudre MOx compactée en pastille. Acier AIM1 sur
SPX, AIM2 sur ASTRID.
</p>
<p
id="689d"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Le tube hexagonal est en acier EM10
</p>
<h2
id="002c"
class="pp nn gu bf no pq pr dy ns ps pt ea nw mk pu pv pw mo px py pz ms qa qb qc qd bk"
>
6.2 Les matériaux structurels
</h2>
<ul class="">
<li
id="a334"
class="lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw ss sd se bk"
>
Le barillet, à l’origine en acier 15 D3, a été
changé suite à une fissure rapide.
</li>
<li
id="a328"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
Les tubes GV de SPX sont en alliage à forte
teneur en nickel, du type Alliage 800.
</li>
<li
id="6603"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
La cuve est en acier austénitique (316LN pour
basse teneur carbone (L) et azote contrôlé
(N)).
</li>
<li
id="b095"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
La robinetterie est en acier inoxydable
austénitique.
</li>
</ul>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my sy">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/1*GtDjsXMhTA9WZmkaIuw68A.png 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/1*GtDjsXMhTA9WZmkaIuw68A.png 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/1*GtDjsXMhTA9WZmkaIuw68A.png 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/1*GtDjsXMhTA9WZmkaIuw68A.png 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/1*GtDjsXMhTA9WZmkaIuw68A.png 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/1*GtDjsXMhTA9WZmkaIuw68A.png 1100w,
https://miro.medium.com/v2/resize:fit:1400/format:webp/1*GtDjsXMhTA9WZmkaIuw68A.png 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
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https://miro.medium.com/v2/resize:fit:720/1*GtDjsXMhTA9WZmkaIuw68A.png 720w,
https://miro.medium.com/v2/resize:fit:750/1*GtDjsXMhTA9WZmkaIuw68A.png 750w,
https://miro.medium.com/v2/resize:fit:786/1*GtDjsXMhTA9WZmkaIuw68A.png 786w,
https://miro.medium.com/v2/resize:fit:828/1*GtDjsXMhTA9WZmkaIuw68A.png 828w,
https://miro.medium.com/v2/resize:fit:1100/1*GtDjsXMhTA9WZmkaIuw68A.png 1100w,
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"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="474"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
</figure>
<h1
id="6ccf"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
7. Exploitation et bilan de SPX
</h1>
<p
id="49ef"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
<em class="ou"
>C’est la partie où je m’énerve. Vous allez
l’être aussi en lisant jusqu’au bout.</em
>
</p>
<p
id="ee19"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>Un prototype arrêté trop tôt</strong
>
</p>
<blockquote class="qw">
<p
id="1a4a"
class="qx qy gu bf qz ra rb rc rd re rf mw du"
>
<em class="sz"
>“ Le simple bon sens dicte la marche à
suivre : puisque l’investissement est fait,
puisque le combustible est disponible, et
puisque les dépenses d’exploitation peuvent
être équilibrées par les fournitures
d’électricité, dépensons le plus tard
possible les sommes inéluctables que
nécessiteront la mise à l’arrêt définitif et
le démantèlement de la centrale. “ </em
>Georges Vendryes
</p>
</blockquote>
<p
id="1db6"
class="pw-post-body-paragraph lz ma gu mb b mc rg me mf mg rh mi mj mk ri mm mn mo rj mq mr ms rk mu mv mw gn bk"
>
<strong class="mb gv"
>Comprendre ses performances
industrielles</strong
>
</p>
<p
id="7db5"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Sur les 10 années d’opération du réacteur :
</p>
<ul class="">
<li
id="b6ee"
class="lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw ss sd se bk"
>
54 mois de procédures administratives pendant
lesquelles le réacteur est en état de
fonctionner, mais n’est pas autorisé
</li>
<li
id="e1e7"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
53 mois de réel fonctionnement
</li>
</ul>
<p
id="5a84"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Deux évènements non nucléaires n’ont pas aidé le
réacteur:
</p>
<ul class="">
<li
id="8e06"
class="lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw ss sd se bk"
>
En 1990, le toit de la salle des machines
s’effondre à cause d’une chute de neige
exceptionnelle.
</li>
<li
id="7143"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
La turbine de 1200MWe n’était pas encore
prête, il a fallu en faire deux de 600MWe.
Cela a conduit à des difficultés de
fonctionnement importantes dans les premières
années et à des baisses notables du
coefficient de disponibilité.
</li>
</ul>
<p
id="3a39"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv">Les fuites sodium</strong>
</p>
<p
id="04c6"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Superphénix aura connu
<strong class="mb gv"
>3 très petites fuites </strong
>de sodium (à comparer à Phénix qui en a eu 32,
et oui le retour d’expérience, ça compte).
</p>
<p
id="a41b"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">Première fuite:</em> mai 1987,
une fuite sodium est constatée sur le barillet.
Cette fuite est causée par la corrosion d’un
acier proposé par le partenaire allemand… Or cet
acier n’était ni utilisé, ni validé sur Phénix.
Cet équipement sera remplacé et cela nécessita
une intervention de 18 mois.
</p>
<p
id="4302"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">Deuxième fuite :</em> en 1990, de
l’air s’infiltre dans la partie supérieure, dans
le ciel d’argon. Cette fuite est causée par un
compresseur de mauvaise fabrication. Cette fuite
a servi de raison aux politiques pour paralyser
le réacteur qui ne pourra pas fonctionner
pendant 4 ans.
</p>
<p
id="8ee5"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">Troisième fuite : </em>en 1995,
une fuite d’argon sur le tube d’alimentation
d’une cloche d’échangeur, est localisée et
réparée sur place directement.
</p>
<p
id="3065"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">Bilan : </em>trois fuites sans
aucun rejet à l’environnement, sans conséquence
radiologique grave.
</p>
<p
id="9bf6"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>Rejets dans l’environnement</strong
>
</p>
<p
id="9886"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">à finir</em>
</p>
<p
id="e541"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>Conséquences sociales de l’arrêt de
SPX</strong
>
</p>
<p
id="fad5"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
L’arrêt fut si brutal que beaucoup de personnes
se sont retrouvées au chômage du jour au
lendemain.
</p>
<p
id="d5a0"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Je vous conseille cet excellent article:
</p>
<div class="ta tb tc td te tf">
<a
href="https://www.contrepoints.org/2015/09/09/221198-larret-de-superphenix-fut-un-desastre-humain?source=post_page-----f23c9a43cc08--------------------------------"
rel="noopener ugc nofollow"
target="_blank"
><div class="tg ab is">
<div class="th ab co cb ti tj">
<h2
class="bf gv ij z rw tk tl tm tn to tp gt bk"
>
L&#x27;arrêt de Superphénix fut un
désastre humain
</h2>
<div class="tq l">
<h3
class="bf b ij z rw tk tl tm tn to tp du"
>
La fermeture de la centrale de
Creys-Malville en 1998
s&#x27;apparente à un suicide
économique et technologique.
</h3>
</div>
<div class="tr l">
<p
class="bf b dv z rw tk tl tm tn to tp du"
>
www.contrepoints.org
</p>
</div>
</div>
<div class="ts l">
<div
class="tt l tu tv tw ts tx ng tf"
></div>
</div></div
></a>
</div>
<p
id="f2ed"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>Justification de l’arrêt de SPX, et aucun
argument ne tient</strong
>
</p>
<p
id="33cd"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<em class="ou">à finir</em>
</p>
<div class="ta tb tc td te tf">
<a
href="https://www.senat.fr/rap/l97-4392/l97-439230.html?source=post_page-----f23c9a43cc08--------------------------------"
rel="noopener ugc nofollow"
target="_blank"
><div class="tg ab is">
<div class="th ab co cb ti tj">
<h2
class="bf gv ij z rw tk tl tm tn to tp gt bk"
>
La politique énergétique de la France :
passion ou raison ? (tome 2) - Sénat
</h2>
<div class="tq l">
<h3
class="bf b ij z rw tk tl tm tn to tp du"
>
Le Sénat a pour missions premières le
vote de la loi, le contrôle du
Gouvernement et l&#x27;évaluation des
politiques…
</h3>
</div>
<div class="tr l">
<p
class="bf b dv z rw tk tl tm tn to tp du"
>
www.senat.fr
</p>
</div>
</div>
<div class="ts l">
<div
class="ty l tu tv tw ts tx ng tf"
></div>
</div></div
></a>
</div>
<h1
id="566a"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
8. La suite de SPX
</h1>
<p
id="76fc"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
Le projet ASTRID, porté par le CEA, visant à
développer un RNR-Na de puissance intermédiaire,
a été abandonné (en réalité repoussé après 2050,
ce qui revient à tuer la compétence et donc
abandonner le projet).
</p>
<p
id="e88c"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Le CEA a récemment essaimé deux structures
privées afin de relancer les concepts de RNR-Na.
L’espoir est désormais à placer dans deux
structures,
<a
class="af qf"
href="https://www.hexana.fr/"
rel="noopener ugc nofollow"
target="_blank"
>Hexana </a
>et
<a
class="af qf"
href="https://otrera.fr/"
rel="noopener ugc nofollow"
target="_blank"
>Otrera</a
>.
</p>
<p
id="fed4"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Les deux concepts reprennent certaines briques
technologiques du projet ASTRID. La différence
notable est sur l’échangeur intermédiaire:
</p>
<ul class="">
<li
id="ab6c"
class="lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw ss sd se bk"
>
Hexana a fait le choix d’un stockage de sels
fondus pour servir de batterie thermique, en
utilisant un sel non réactif avec le sodium
dans l’échangeur
</li>
<li
id="b0df"
class="lz ma gu mb b mc sf me mf mg sg mi mj mk sh mm mn mo si mq mr ms sj mu mv mw ss sd se bk"
>
Otrera a fait le choix de l’échangeur
sodium-diazote du projet ASTRID.
</li>
</ul>
<p
id="660d"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Ces deux start-up proposent la technologie la
plus mature de tout le spectre du nucléaire
innovant, en France comme à l’international. On
parle de 400 années réacteurs en fonctionnement.
Soit plus que les RNR-Pb (plomb), RNR-gaz et RSF
(sels fondus) réunis. Nous en avons eu trois en
France, à différentes puissances permettant de
valider le concept.
</p>
<p
id="a290"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Souhaitons que cette fois-ci la France comprenne
qu’elle a rendez-vous avec son avenir.
</p>
<h1
id="7476"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
9. Conclusion
</h1>
<p
id="6c76"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
J’espère vous avoir donné des éléments utiles
pour comprendre les RNR-Na et le génie derrière
Superphénix. Vous saurez quoi répondre quand on
vous parlera des soi-disant “dangers” de SPX.
</p>
<p
id="514b"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<strong class="mb gv"
>Cet article est dédié aux 3000 techniciens et
ingénieurs, hommes et femmes, privés de leur
formidable machine, avec les conséquences
sociales associées à cette brutale fermeture.
Superphénix a été tué par l’ignorance des
politiques. La France avait une avance
considérable qu’elle a aujourd’hui perdu.
Soyons collectivement à la hauteur de
l’héritage de nos anciens, à qui je n’ai
qu’une chose à dire: merci.</strong
>
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div class="mx my tz">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/0*036SOrMqmhIsBeQq.jpg 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/0*036SOrMqmhIsBeQq.jpg 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/0*036SOrMqmhIsBeQq.jpg 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/0*036SOrMqmhIsBeQq.jpg 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/0*036SOrMqmhIsBeQq.jpg 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/0*036SOrMqmhIsBeQq.jpg 1100w,
https://miro.medium.com/v2/resize:fit:1224/format:webp/0*036SOrMqmhIsBeQq.jpg 1224w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 612px"
type="image/webp" />
<source
data-testid="og"
srcset="
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https://miro.medium.com/v2/resize:fit:720/0*036SOrMqmhIsBeQq.jpg 720w,
https://miro.medium.com/v2/resize:fit:750/0*036SOrMqmhIsBeQq.jpg 750w,
https://miro.medium.com/v2/resize:fit:786/0*036SOrMqmhIsBeQq.jpg 786w,
https://miro.medium.com/v2/resize:fit:828/0*036SOrMqmhIsBeQq.jpg 828w,
https://miro.medium.com/v2/resize:fit:1100/0*036SOrMqmhIsBeQq.jpg 1100w,
https://miro.medium.com/v2/resize:fit:1224/0*036SOrMqmhIsBeQq.jpg 1224w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 612px" />
<img
alt=""
class="bh ng nh c"
width="612"
height="306"
loading="lazy"
role="presentation"
/></picture>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Plaque commémorative devant SPX.
</figcaption>
</figure>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my ua">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/1*I7hnkz4wWTeA1Y0PhktU5A.png 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/1*I7hnkz4wWTeA1Y0PhktU5A.png 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/1*I7hnkz4wWTeA1Y0PhktU5A.png 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/1*I7hnkz4wWTeA1Y0PhktU5A.png 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/1*I7hnkz4wWTeA1Y0PhktU5A.png 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/1*I7hnkz4wWTeA1Y0PhktU5A.png 1100w,
https://miro.medium.com/v2/resize:fit:1400/format:webp/1*I7hnkz4wWTeA1Y0PhktU5A.png 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
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https://miro.medium.com/v2/resize:fit:786/1*I7hnkz4wWTeA1Y0PhktU5A.png 786w,
https://miro.medium.com/v2/resize:fit:828/1*I7hnkz4wWTeA1Y0PhktU5A.png 828w,
https://miro.medium.com/v2/resize:fit:1100/1*I7hnkz4wWTeA1Y0PhktU5A.png 1100w,
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"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="571"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
<figcaption
class="ni ff nj mx my nk nl bf b bg z du"
>
Photo tirée de “Superphenix Technical and
Scientific Achievements” par Joël Guidez.
</figcaption>
</figure>
<p
id="f5f0"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Le phénix renait toujours de ses cendres. Merci
de m’avoir lu 🧡.
</p>
<figure
class="na nb nc nd ne nf mx my paragraph-image"
>
<div
role="button"
tabindex="0"
class="oq or fj os bh ot"
>
<div class="mx my ub">
<picture
><source
srcset="
https://miro.medium.com/v2/resize:fit:640/format:webp/0*J-LujTym-6O_8Qdq 640w,
https://miro.medium.com/v2/resize:fit:720/format:webp/0*J-LujTym-6O_8Qdq 720w,
https://miro.medium.com/v2/resize:fit:750/format:webp/0*J-LujTym-6O_8Qdq 750w,
https://miro.medium.com/v2/resize:fit:786/format:webp/0*J-LujTym-6O_8Qdq 786w,
https://miro.medium.com/v2/resize:fit:828/format:webp/0*J-LujTym-6O_8Qdq 828w,
https://miro.medium.com/v2/resize:fit:1100/format:webp/0*J-LujTym-6O_8Qdq 1100w,
https://miro.medium.com/v2/resize:fit:1400/format:webp/0*J-LujTym-6O_8Qdq 1400w
"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px"
type="image/webp" />
<source
data-testid="og"
srcset="
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https://miro.medium.com/v2/resize:fit:750/0*J-LujTym-6O_8Qdq 750w,
https://miro.medium.com/v2/resize:fit:786/0*J-LujTym-6O_8Qdq 786w,
https://miro.medium.com/v2/resize:fit:828/0*J-LujTym-6O_8Qdq 828w,
https://miro.medium.com/v2/resize:fit:1100/0*J-LujTym-6O_8Qdq 1100w,
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"
sizes="(min-resolution: 4dppx) and (max-width: 700px) 50vw, (-webkit-min-device-pixel-ratio: 4) and (max-width: 700px) 50vw, (min-resolution: 3dppx) and (max-width: 700px) 67vw, (-webkit-min-device-pixel-ratio: 3) and (max-width: 700px) 65vw, (min-resolution: 2.5dppx) and (max-width: 700px) 80vw, (-webkit-min-device-pixel-ratio: 2.5) and (max-width: 700px) 80vw, (min-resolution: 2dppx) and (max-width: 700px) 100vw, (-webkit-min-device-pixel-ratio: 2) and (max-width: 700px) 100vw, 700px" />
<img
alt=""
class="bh ng nh c"
width="700"
height="700"
loading="lazy"
role="presentation"
/></picture>
</div>
</div>
</figure>
<h1
id="25ca"
class="nm nn gu bf no np nq nr ns nt nu nv nw nx ny nz oa ob oc od oe of og oh oi oj bk"
>
Sources
</h1>
<p
id="29f2"
class="pw-post-body-paragraph lz ma gu mb b mc ok me mf mg ol mi mj mk om mm mn mo on mq mr ms oo mu mv mw gn bk"
>
[1] Source principale, monographie CEA RNR-Na.
</p>
<div class="ta tb tc td te tf">
<a
href="https://www.cea.fr/multimedia/Pages/editions/ouvrages/monographies-nucleaire/reacteurs-nucleaires-caloporteur-sodium.aspx?source=post_page-----f23c9a43cc08--------------------------------"
rel="noopener ugc nofollow"
target="_blank"
><div class="tg ab is">
<div class="th ab co cb ti tj">
<h2
class="bf gv ij z rw tk tl tm tn to tp gt bk"
>
les réacteurs nucléaires à caloporteur
sodium
</h2>
<div class="tq l">
<h3
class="bf b ij z rw tk tl tm tn to tp du"
>
Cette monographie décrit
l&#x27;historique et le retour
d&#x27;expérience technique accumulé
sur ces réacteurs, dont les trois…
</h3>
</div>
<div class="tr l">
<p
class="bf b dv z rw tk tl tm tn to tp du"
>
www.cea.fr
</p>
</div>
</div>
<div class="ts l">
<div
class="uc l tu tv tw ts tx ng tf"
></div>
</div></div
></a>
</div>
<p
id="2b7e"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
Source [2]
</p>
<p
id="cb43"
class="pw-post-body-paragraph lz ma gu mb b mc md me mf mg mh mi mj mk ml mm mn mo mp mq mr ms mt mu mv mw gn bk"
>
<a
class="af qf"
href="https://inis.iaea.org/collection/NCLCollectionStore/_Public/52/111/52111240.pdf"
rel="noopener ugc nofollow"
target="_blank"
>https://inis.iaea.org/collection/NCLCollectionStore/_Public/52/111/52111240.pdf</a
>
</p>
<p
id="7808"
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text: "L’aventure Superphénix🔥",
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text: "Superphénix… s’il est un réacteur célèbre en France, c’est bien lui. J’en parle souvent, avec des regrets, mais aussi avec la fierté de vivre dans le pays qui a développé un réacteur unique au monde jamais égalé. En son temps, il était le roi de tous les réacteurs, du haut de ses 1240 MW électriques, offrant un réél potentiel d’indépendance énergétique à la France.",
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text: "Et si on en parlait, en prenant le temps, en développant les concepts ?",
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text: "Pour celles & ceux n’ayant pas un attrait prononcé pour la technique, les premiers paragraphes de cet article établiront une présentation rapide de SPX. La suite ira plus en profondeur, en s’appuyant sur les livres de Joël Guidez, la monographie du CEA sur les RNR à caloporteurs sodium, et des documents de l’IRSN (sources à la fin de l’article).",
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text: "Superphénix - centrale nucléaire de Creys-Malville.",
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text: "Vous avez dit Superphénix ?",
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text: "Superphénix (désigné par le sigle SPX1 ou SPX) est un réacteur nucléaire à neutrons rapides (RNR) dont le caloporteur est le sodium (symbole Na) sous forme liquide.",
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text: "Neutron : c’est la particule élémentaire sans charge électrique qui est responsable des fissions des éléments fissiles (uranium 235 & plutonium 239 principalement).",
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text: "Neutron rapide : c’est un neutron de forte énergie cinétique (Ec = 0.5*masse*vitesse²). On utilise ce terme en opposition aux neutrons thermiques (plus lents) utilisés dans un réacteur à eau sous pression, ceux que la France exploite actuellement. Un neutron rapide n’a donc pas été ralenti dans un modérateur. Un neutron rapide a une vitesse d’au moins 13800 km\u002Fs, et un neutron thermique d’au moins 2.2 km\u002Fs.",
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text: "Les neutrons rapides sont issus directement de la fission. Ici c’est un réacteur avec un modérateur, qui va venir ralentir les neutrons rapides par une série de chocs. Les neutrons lents ont une probabilité de fission avec les noyaux d’U235 plus importante, et c’est ainsi que la réaction en chaîne est maintenue.",
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text: "Caloporteur : vient du latin calor pour chaleur. C’est donc le nom donné au fluide qui circule pour extraire la chaleur. Dans un réacteur nucléaire il peut y en avoir plusieurs. Le plus connu est l’eau, qui sert à la fois de fluide d’échange au circuit primaire, secondaire et tertiaire.",
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text: "Dans un réacteur à eau légère, on dit qu’on utilise des neutrons thermiques, ou lents. Ils ont perdu leur énergie cinétique par une succession de chocs, et cela permet d’augmenter sa “probabilité de fission” sur l’uranium 235. Et donc, pourquoi les neutrons “rapides” ? Pour aller fissionner plus facilement des atomes qui ne le sont pas avec des neutrons thermiques ! La courbe ci-dessous donne la “probabilité d’interaction” selon l’énergie du neutron. En rapide (1MeV donc), on voit une nette différence entre la capture et la fission. Autrement dit, dans le domaine rapide, probabilité de fissionner est plus de 10 fois supérieure à celle de l’absorption.",
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text: "Mais on peut aussi fertiliser les atomes d’uranium 238 ! En le transformant en Pu239 justement, qui lui est fissile… On en reparle juste en-dessous dans la partie “Surgénérateur ou incinérateur ?”…",
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text: "Quelles sont les différences entre un REP (réacteur actuel), et un RNR-Na?",
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text: "Le changement principal intervient sur le circuit primaire, comme détaillé ci-dessous. Un échangeur intermédiaire, lui aussi en sodium, est intercalé pour extraire la chaleur du cœur et la transmettre aux générateurs de vapeur.",
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text: "Schéma d’un REP sans aéroréfrigérant \u002F\u002F Schéma de SPX",
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text: "Les différences seront explicitées plus bas dans la partie 3: “ La technologie RNR-Na”.",
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text: "Selon l’organisation du cœur et ce qu’on met dans les assemblage combustible, plusieurs possibilités s’offrent aux RNR-Na. Deux familles nous intéressent. Les isotopes du plutonium et les actinides mineurs.",
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text: "Les stocks de plutonium sont condamnés à augmenter à court terme, ils augmentent même dans les pays qui le recyclent (MOx), car les réacteurs actuels n’en font pas disparaître assez. Ce qu’on voit dans l’image ci-dessous est la masse accumulée selon le temps en fonction du cycle. Le cycle ouvert est l’option actuellement poursuivie en France. Le scénario MIX (valorisant les MOx) et RNR permettent d’abaisser considérablement ces stocks.",
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text: "En enlevant l’enveloppe d’uranium 238 autour du cœur, Superphénix pouvait devenir sous-générateur : il pouvait consommer plus de plutonium 239 qu’il n’en créait. Cela permettait donc d’incinérer les déchets accumulés les plus problématiques, et sans devoir miner un gramme d’uranium naturel. Superphénix pouvait également transmuter les actinides pour en faire des déchets à vie courte. Le RNR-Na est le seul concept mature capable de faire cela. Cette configuration a été celle de SPX durant toute son existence.",
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text: "Pour les actinides, il est possible de remplacer certaines alvéoles par des assemblages spéciaux pour les faire fissionner, et réduire drastiquement leur durée de vie (de plusieurs centaines de milliers d’années à quelques centaines).",
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text: "La capture neutronique sur l’uranium 238 à l’intérieur du cœur ainsi que dans les enveloppes en périphéries de cœur pouvait produire plus de plutonium qu’il n’en consommait. Ainsi, il pouvait régénérer son propre stock de combustible à partir de matière fertile. Le cœur de SPX, bien que capable de passer en mode surgénération, n’a jamais été fait, mais cela était bel et bien prévu par l’exploitant.",
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text: "1. Pourquoi faire Superphénix ?",
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text: "2. L’histoire des RNR, du projet Manhattan jusqu’à SPX2",
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text: "1. Pourquoi faire Superphénix ?",
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text: "Je reprendrai certains des mots de Georges Vendryes (1920–2014), grand serviteur du nucléaire français, dans “Superphénix pourquoi ?”, ouvrage dont je recommande la lecture, il est accessible à toutes et tous.",
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text: "“Le premier pays qui mettra au point un réacteur nucléaire surgénérateur en tirera un avantage commercial décisif.” Enrico Fermi, 1945.",
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text: "Le grand-père de Superphénix, Rapsodie",
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text: "La France d’après 1945 se relève doucement et créée en 1945 le Commissariat à l’Energie Atomique, pour que la France soit souveraine sur les technologies nucléaires militaires et civiles. La recherche sur les neutrons rapides en France part avec 10 ans de retard sur les Etats-Unis (Clementine, EBR-1), l’URSS (BR2, 5 puis BR10) et la Grande-Bretagne (DFR). En 1958, le CEA l’avant-projet sommaire de Rapsodie, première “pile expérimentale à neutron rapides refroidie au sodium” (on appellerait ça un réacteur nucléaire aujourd’hui). L’objectif est d’acquérir des données expérimentales pour lancer plus tard un prototype dont on pourrait convertir l’énergie du cœur. L’aventure des neutrons rapides commence alors à Cadarache, dans le Sud de la France. Sa construction commença en 1962 et s’acheva en 1966, pour une première divergence et l’atteinte de sa pleine puissance (20MWth) en 1967. Il fut exploité pendant 15 ans, et a ouvert la voie à Phénix.",
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text: "Son père, Phénix.",
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text: "EDF et le CEA signent en 1969 un protocole d’exploitation commun. Le réacteur fera 250MWe, permettant de garder les dimensions industrielles des groupes turbo-alternateurs disponibles à l’époque. Début des travaux en 1968 et divergence en 1973, pleine puissance en 1974. Malgré quelques incidents propres à tout prototype, le réacteur fonctionne 15 ans de façon remarquable, et est le premier à utiliser le plutonium qu’il a lui-même produit. Il atteint un taux de régénération de 1.16 (16% de matière fissile en plus à la fin du cycle par rapport au début). Le concept de surgénérateur est validé !",
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text: "La naissance de Superphénix.",
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text: "Fin des années 70, après deux crises pétrolières, et après avoir valider un concept de RNR de grande puissance, la coopération européenne pour l’échelon industriel se met en place. Anglais, belges, hollandais, allemands, italiens et français travaillent ensemble à la construction de SPX. Le prototype de 1200MWe commencé en 1976 qui atteint sa pleine puissance en 1986. A l’époque EDF construisait les 900MWe et concevait les futurs 1300MWe. L’objectif était de se placer au même niveau que les réacteurs de puissance.",
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text: "La volonté de fermer le cycle du combustible français",
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text: "Les qualités des RNR du point de vue du cycle sont remarquables. Comme expliqué plus haut, les deux configurations de cœur de type incinérateur ou surgénérateur donnent à SPX un avantage considérable sur tous les autres réacteurs à neutrons thermiques (qui constituent au moins 95% des réacteurs actuels).",
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text: "Plutonium. Actuellement en France, il est utilisé dans les REP sous forme de MOx (“mix d’oxydes U-Pu”), mais il ne peut être utilisé qu’une fois, sa qualité isotopique se dégradant (c’est à dire que la proportion des isotopes pairs, non fissiles, augmente). Le multi-recyclage efficace ne peut avoir lieu que grâce dans des RNR. Nous disposons aussi des stocks de MOX usés (120 t\u002Fan), qui ne sont pas valorisés actuellement malgré leur immense potentiel énergétique.",
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text: "Autres ressources valorisables. L’uranium de retraitement appauvri (800 t\u002Fan) et l’uranium de retraitement réutilisé (140 t\u002Fan), sont également actuellement très peu valorisés, alors qu’ils pourraient servir de combustible dans un parc de réacteurs rapides. Enfin, mais cela est encore à confirmer, il est possible sur le papier de convertir les actinides mineurs par transmutation ce qui diminuerait encore la quantité et la toxicité de ces déchets ultimes. Les déchets les plus complexes à gérer sont actuellement produits par le parc français à hauteur d’environ 40 t\u002Fan, ce qui est ridicule au vue de l’énergie produite mais reste néanmoins un enjeu de gestion (stratégie d’entreposage et de refroidissement). Cela sera détaillé plus loin.",
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text: "2. L’histoire des RNR, du projet Manhattan jusqu’à SPX2",
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text: "C’est important de comprendre la génèse de l’idée derrière le RNR. Ce concept est en réalité apparu dans les esprits des physiciens à peu près au même moment que celui des réacteurs à modérateurs.",
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text: "Enrico Fermi, futur prix Nobel de physique, qui travaillait alors sur la pile de Chicago, a été le premier à étudier les neutrons rapides. Il a remarqué que les neutrons lents causaient plus fréquemment des fissions que les neutrons rapides, découvrant alors le principe de section efficace. Le projet Manhattan achevé, la recherche sur les applications de la fission nucléaire allait bientôt devenir un enjeu majeur pour cette deuxième moitié du XXe siècle.",
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text: "“L’énergie nucléaire est une sacrée façon de faire bouillir de l’eau“, Albert Einstein (1879–1955).",
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text: "1935 Frédéric Joliot-Curie prononce ces mots en conclusion de sa conférence qu’il donne après la réception de son prix Nobel de chimie: “Nous sommes en droit de penser que les chercheurs, construisant ou brisant les atomes à volonté, sauront réaliser des transmutations à caractère explosif, véritables réactions chimiques à chaînes. Si de telles transformations arrivent à se propager dans la matière, on peut concevoir l’énorme libération d’énergie utilisable qui aura lieu”.",
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text: "1942 La pile de Chicago est en place et le 2 décembre 1942 à 15h25, la première réaction en chaîne artificielle auto-entretenue débute.",
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text: "1945Enrico Fermi propose le concept de réacteur surgénérateur. Un réacteur produisant plus de matière fissile qu’il n’en consomme.",
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text: "1946Le premier réacteur nucléaire à neutrons rapides, Clementine, diverge. Il a un caloporteur au mercure. Son objectif était d’étudirr les propriétés nucléaires de plusieurs matériaux à la suite du succès du projet Manhattan. Ce réacteur a servi à de nombreuses expériences, comme prouver la possibilité de faire un surgénérateur civil, ou encore mesurer les sections efficaces de plusieurs isotopes.",
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text: "1951Le premier réacteur nucléaire électrogène, EBR-I pour Experimental Breeder Reactor I, produit assez de puissance pour allumer 4 ampoules. Son caloporteur est un eutectique sodium-potassium (Na-K).",
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text: "1956Création du consortium européen EUROCHEMIC, première agence européenne de coopération technique nucléaire.",
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text: "1958Début du fonctionnement de l’unité de retraitement du plutonium UP1 à Marcoule.",
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text: "1962Construction de Rapsodie, premier RNR-Na en France, critique en 1967. 20MWth. Fonctionnera jusqu’en 1983.",
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text: "1968Construction de phénix par le CEA et EDF. 560MWth. Il fonctionnera jusqu’en 2010.",
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text: "1992Le redémarrage de Superphénix est soumis à la réalisation préalable d’une étude (Rapport Curien) sur la contribution que pourrait apporter Superphénix à l’incinération des déchets radioactifs. Cette étude confirme l’intérêt de SPX pour ce sujet, et le redémarrage est autorisé le 17 décembre 1992.",
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text: "3. Pourquoi le sodium ?",
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text: "Les RNR ont autant de design que de caloporteurs. Certains choisissent des métaux liquides purs (Na, Pb, Hg), d’autres des eutectiques (Pb-Bi, Na-K), ou encore le gaz (He). Certains choisissent aussi l’option des sels (chlorure ou fluorure). Le choix du sodium présente un certain nombre d’avantages et la famille de RNR ayant le plus de retour d’expérience dans le monde est de loin celle du sodium.",
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text: "Un certain nombre de critères doivent s’appliquer au caloporteur d’un RNR. Le premier, assez logiquement, est sa transparence aux neutrons, afin de modérer peu. On cherche donc un matériau faiblement absorbant et à faible pouvoir de ralentissement, ce qui exclut de fait la plupart des matériaux légers.",
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text: "Ensuite, on veut un caloporteur efficace, il doit donc avoir une forte capacité calorifique et une bonne conductivité thermique. Son écoulement en cœur doit être excellent et ne pas demander un effort trop important aux pompes primaires, il doit donc être peu visqueux.",
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text: "Ensuite, il doit être capable d’encaisser les transitoires en restant monophasique liquide, il faut éviter qu’il se solidifie et qu’il s’évapore.",
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text: "Le caloporteur doit être aussi pur que possible pour éviter les produits d’activation dans le circuit, ce qui compliquerait la maintenance. On veut également éviter qu’il soit corrosif pour les structures internes.",
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text: "Enfin, il doit être disponible à bas coût, en quantité industrielle, et le plus pur possible.",
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text: "Bilan pour le sodium : ses températures de fusion (97,8°C) et d’ébullition (883°C) permettent, à 500°C, une utilisation à la pression atmosphérique. Il a une très bonne conductibilité thermique (100 fois celle de l’eau). Il absorbe très peu les neutrons et a une faible capacité à les ralentir (mais cette composante n’est pas nulle pour autant, nous le verrons dans la partie sûreté). Le sodium ne s’active pas non plus est est peu corrosif. Il est excellent d’un point de vue neutronique et thermohydraulique mais mauvais sur la physico-chimie du fait de la réaction Na-H2O très exothermique et de son inflammation au contact de l’air. Le sodium n’est pas cher et est adapté à l’usage industriel.",
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text: "On utilise communément une unité d’énergie appelée électron-volt pour l’énergie cinétique des neutrons.",
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text: "Superphénix est un réacteur à neutrons rapides (RNR), ce qui signifie que sa population de neutron sera (très majoritairement) dans le “spectre” rapide, de 10⁵eV à 2*10⁷eV, comme le montre la courbe orange ci-dessous.",
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text: "Coefficient de contre réaction. Parler de la CFV non échelonable.",
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text: "à finir",
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text: "Le combustible a une géométrie hexagonale (carrée en REP), et est disposé dans des “aiguilles ” (“crayons” en REP). La géométrie en aiguille est choisie pour sa compacité, un combustible RNR-Na doit avoir au moins 15% de plutonium.",
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text: "Dans un RNR-Na, il y a un échangeur supplémentaire, intercalé entre le circuit primaire et le circuit turbine. Pourquoi ?",
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text: "On veut éviter le contact entre l’eau du circuit turbine et le sodium primaire (réaction très exothermique, boom)…",
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text: "Deux concepts d’organisation de ce circuit intermédiaire sont proposés. La différence repose sur la localisation de l’échangeur intermédiaire, dans la cuve (concept intégré) ou en dehors (concept à boucles, comme sur REP). Le caloporteur utilisé dans cet échangeur est également du sodium, après avoir écarté l’option de l’eutectique Pb-Bi. Des concepts récents (Hexana) proposent d’utiliser un sel fondu.",
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text: "Les générateurs de vapeur (GV) sont hélicoïdaux sur SPX, contrairement à ceux des REP, et encore différents des GV en épingle de Phénix. L’avantage de cette géométrie est qu’elle présente une grande longueur (80m). Les GV de SPX sont conçus en un seul morceau, comme sur REP, moins chers mais plus durs à changer. Les tubes sont en Alliage 800. Les caractéristiques sont détaillées ci-dessous. Le GV avait beau être le premier du genre, aucun incident majeur n’a été déclaré pendant ses 748 jours d’opérations.",
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text: "C’est assez particulier sur SPX, il y a deux cuve. Une cuve dans une autre. La cuve la plus intérieure contient l’ensemble du circuit primaire, et la cuve de sécurité qui l’entoure permet de contrôler les fuites sodium et de valoriser la convection naturelle de ce dernier, et donc en évacuant la chaleur résiduelle, ce qui permet d’éviter l’évaporation du sodium. Sur Phénix, la faible puissance relative à la surface de cuve permettait de refroidir uniquement par rayonnement de la face externe de la cuve.",
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text: "C’est une pièce multifonction. Il sert à fermer le circuit primaire par le haut, assurant l’étanchéité. Comme sur un REP, le BCC supporte et positionne les mécanismes de commande des barres et l’instrumentation de surveillance du cœur. Il a aussi un rôle de protection biologique et thermique. Par rapport à un REP, le BCC a aussi une fonction hydraulique, il dévie les jets de sodium à la sortie du cœur.",
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text: "Déjà, le réacteur dispose de grappes d’arrêt pour stopper la réaction en chaîne, elles sont placées en haut (cf. schéma ci-dessous). L’effet Xénon n’est pas présent, simplifiant le contrôle de la réactivité du cœur. Le centre du cœur, là où il est le plus chaud, induit des variations de densité du sodium, contribuant à des insertions ponctuelles de réactivité. L’objectif est de se prémunir en concevant un cœur CFV (faible vidange) comme le projet ASTRID. L’effet est d’autant plus fort que le cœur est grand.",
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text: "Le sodium a une plus grande marge à l’ébullition que l’eau par rapport au fonctionnement normal. L’ inertie thermique du sodium ( résistance au changement température lors d’un transitoire). Des systèmes diversifiés sont mis en place pour évacuer la puissance résiduelle, dont des échangeurs sodium-air. Sur SPX, le DRACS est le BPR sont passifs à 4 boucles. Le RVACS est actif à deux boucles. Il n’y a pas de SGOSHDR sur SPX.",
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text: "Première barrière (gaine combustible) : la conductivité thermique élevée du sodium (x70 par rapport à l’eau) assure un coefficient d’échange important entre les gaines et le sodium. Concernant les ruptures de gaine, elles sont de deux types, ouverte ou gazeuse. Les RNR français sont équipés du système DND (Détection de Neutrons Différés) pour détecter les ruptures ouvertes de gaine. L’assemblage défectueux est ensuite identifié et retiré du cœur (on s’interdit de fonctionner en gaines percées). Dans le cas des ruptures par rejet de gaz de fission, des rejets peuvent alors avoir lieu par les soupapes de protection du circuit d’argon du ciel de pile",
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text: "La deuxième barrière est assez complexe à définir sur RNR-Na, on va donc regarder seulement le concept intégré ici (type SPX).",
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text: "En résumé, tout ce qui constitue la cuve et sa partie supérieure, plus les traversées. Cette barrière n’est pas étanche. Il existe des fuites d’argon au niveau de la fermeture supérieure par l’ouverture des soupapes pour réguler la pression du “ciel de pile”. Ces fuites sont contrôlées et mesurées régulièrement.",
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text: "La troisième barrière (bâtiment en béton très résistant) la très faible pression primaire simplifie grandement les problématiques de fuite et de tenue de l’enceinte de confinement. En revanche, la réaction sodium-eau est à surveiller, ne serait-ce qu’avec l’humidité ambiante. Certains designs proposent de changer l’eau par du CO2 supercritique.",
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text: "Concernant les accidents graves, les normes à l’époque de Phénix n’imposaient pas de système de mitigation. SPX avait quand à lui un récupérateur à débris de corium dans sa cuve. On l’appelait le cendrier, il était originellement conçu pour résister à la fusion complète de 7 assemblages, la fusion totale étant jugée trop improbable en raison des caractéristiques de sûreté du cœur.",
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text: "Cette partie est la plus important pour comprendre l’intérêt des RNR-Na dans une optique de gestion durables des matières radioactives françaises. La France est assise sur une mine d’or qui ne demande qu’à être exploité, à la différence notable que, cette fois, l’or est déjà miné et ne demande qu’à être valorisé.",
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text: "En l’état actuel du cycle français, le parc produit environ 10 tonnes de Pu par an. Les REP viennent donc se placer comme l’étape préliminaire (et indispensable) à l’établissement d’une filière rapide qui a besoin de plutonium pour démarrer ses premiers cœurs. L’objectif à très long terme (plusieurs décennies) est la surgénération, qui permet ensuite à la filière de s’autoalimenter. Ainsi il est nécessaire de maintenir la filière REP pour accompagner les premiers RNR.",
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text: "Déjà, de quels isotopes parle-t-on ? Dans l’ordre d’importance, l’Américium (Am 241, Am 243), le Curium (Cm 244, Cm 245) et le Neptunium (Np 237).",
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text: "Combustible usé de REP-UOx",
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text: "L’objectif est double, obtenir des colis moins toxiques…et beaucoup moins chauds ! Je ne vous dirai pas que les déchets ne seront plus un problème, mais la transmutation des AM ouvre la voie à des modes de gestion beaucoup plus simples. De plus, cela permettrait d’utiliser CIGEO encore mieux, du fait de la possibilité d’augmentation de concentration de matière dans les alvéoles, la chaleur résiduelle étant moins élevée ! Ci-dessous, les contributions des AM à la radiotoxicité des colis et à leur chaleur.",
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text: "Convertir les actinides mineurs en énergie permettrait de diminuer leur radiotoxicité. (cf. [1] p.171)",
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text: "Mais cela ferait aussi des colis moins chauds à gérer. (cf. [1] p.171)",
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text: "Les processus chimiques impliqués dans le retraitement et l’extraction des actinides mineurs dépassent mes compétences, mais les personnes intéressées peuvent toujours aller lire la monographie CEA sur la séparation des actinides des combustibles usés (disponible ici). C’est un sujet passionnant qui mériterait un article entier, mais n’étant pas chimiste je ne m’y risquerai pas.",
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text: "En supposant une extraction efficace dans le combustible de ces AM, on peut maintenant regarder les potentiels usages en RNR. Déjà, la neutronique du RNR est plus favorable à la transmutation des AM:",
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text: "A comprendre ainsi: “Le Neptunium 237 a 30 fois plus de chance d’être capturé que de fissionner en REP-MOx. Cela passe à 5.3 en RNR-MOx”.",
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text: "“ Le simple bon sens dicte la marche à suivre : puisque l’investissement est fait, puisque le combustible est disponible, et puisque les dépenses d’exploitation peuvent être équilibrées par les fournitures d’électricité, dépensons le plus tard possible les sommes inéluctables que nécessiteront la mise à l’arrêt définitif et le démantèlement de la centrale. “ Georges Vendryes",
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text: "Première fuite: mai 1987, une fuite sodium est constatée sur le barillet. Cette fuite est causée par la corrosion d’un acier proposé par le partenaire allemand… Or cet acier n’était ni utilisé, ni validé sur Phénix. Cet équipement sera remplacé et cela nécessita une intervention de 18 mois.",
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