A comparison between fission gas release data and FEMAXI-IV code calculations
Identifieur interne : 001964 ( Main/Exploration ); précédent : 001963; suivant : 001965A comparison between fission gas release data and FEMAXI-IV code calculations
Auteurs : T. Nakajima [Japon] ; H. Saito [Japon]Source :
- Nuclear Engineering and Design [ 0029-5493 ] ; 1987.
Abstract
The FEMAXI-IV code is an extension of the earlier version FEMAXI-III. The primary improvement in the new version is the provision for treating the fuel rod behavior during an operational transient. For this purpose, the time-dependent models are used for heat conduction, fission gas release, and mixing of the released gas with the plenum gas.In FEMAXI-IV, the fission gas release model was thoroughly revised from the previous version. It is based on the fission gas release model presented by White and Tucker. The model takes into account the following mechanisms: •- diffusion of gas atoms to the grain boundary;•- sweeping of gas atoms by grain growth;•- precipitation of gas atoms into intragranular gas bubbles;•- resolution of gas atoms from intragranular and grain boundary gas bubbles;•- fission gas release due to bubble interconnection.The model was incorporated into FEMAXI-IV and code calculations were compared with the fission gas release data obtained in the Inter-Ramp and Over-Ramp experiments.This paper describes the fission gas release model involved and results of calculations.
Url:
DOI: 10.1016/0029-5493(87)90055-0
Affiliations:
Links toward previous steps (curation, corpus...)
- to stream Istex, to step Corpus: 001307
- to stream Istex, to step Curation: 001307
- to stream Istex, to step Checkpoint: 001468
- to stream Main, to step Merge: 001A71
- to stream Main, to step Curation: 001964
Le document en format XML
<record><TEI wicri:istexFullTextTei="biblStruct"><teiHeader><fileDesc><titleStmt><title>A comparison between fission gas release data and FEMAXI-IV code calculations</title><author><name sortKey="Nakajima, T" sort="Nakajima, T" uniqKey="Nakajima T" first="T." last="Nakajima">T. Nakajima</name></author><author><name sortKey="Saito, H" sort="Saito, H" uniqKey="Saito H" first="H." last="Saito">H. Saito</name></author></titleStmt><publicationStmt><idno type="wicri:source">ISTEX</idno><idno type="RBID">ISTEX:D98B61C4CC7A234BC5DCF7FC162819A37D94FF28</idno><date when="1987" year="1987">1987</date><idno type="doi">10.1016/0029-5493(87)90055-0</idno><idno type="url">https://api.istex.fr/document/D98B61C4CC7A234BC5DCF7FC162819A37D94FF28/fulltext/pdf</idno><idno type="wicri:Area/Istex/Corpus">001307</idno><idno type="wicri:Area/Istex/Curation">001307</idno><idno type="wicri:Area/Istex/Checkpoint">001468</idno><idno type="wicri:explorRef" wicri:stream="Istex" wicri:step="Checkpoint">001468</idno><idno type="wicri:doubleKey">0029-5493:1987:Nakajima T:a:comparison:between</idno><idno type="wicri:Area/Main/Merge">001A71</idno><idno type="wicri:Area/Main/Curation">001964</idno><idno type="wicri:Area/Main/Exploration">001964</idno></publicationStmt><sourceDesc><biblStruct><analytic><title level="a">A comparison between fission gas release data and FEMAXI-IV code calculations</title><author><name sortKey="Nakajima, T" sort="Nakajima, T" uniqKey="Nakajima T" first="T." last="Nakajima">T. Nakajima</name><affiliation wicri:level="1"><country xml:lang="fr">Japon</country><wicri:regionArea>Fuel Reliability Laboratory I, Department of Fuel Safety Research, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken</wicri:regionArea><wicri:noRegion>Ibaraki-ken</wicri:noRegion></affiliation></author><author><name sortKey="Saito, H" sort="Saito, H" uniqKey="Saito H" first="H." last="Saito">H. Saito</name><affiliation wicri:level="1"><country xml:lang="fr">Japon</country><wicri:regionArea>Century Research Center Corp., 3-2 Nihonbashi-honcho, Chuou-ku, Tokyo 103</wicri:regionArea><placeName><settlement type="city">Tokyo</settlement><region type="région">Région de Kantō</region></placeName></affiliation></author></analytic><monogr></monogr><series><title level="j">Nuclear Engineering and Design</title><title level="j" type="abbrev">NED</title><idno type="ISSN">0029-5493</idno><imprint><publisher>ELSEVIER</publisher><date type="published" when="1987">1987</date><biblScope unit="volume">101</biblScope><biblScope unit="issue">3</biblScope><biblScope unit="page" from="267">267</biblScope><biblScope unit="page" to="279">279</biblScope></imprint><idno type="ISSN">0029-5493</idno></series><idno type="istex">D98B61C4CC7A234BC5DCF7FC162819A37D94FF28</idno><idno type="DOI">10.1016/0029-5493(87)90055-0</idno><idno type="PII">0029-5493(87)90055-0</idno></biblStruct></sourceDesc><seriesStmt><idno type="ISSN">0029-5493</idno></seriesStmt></fileDesc><profileDesc><textClass></textClass><langUsage><language ident="en">en</language></langUsage></profileDesc></teiHeader><front><div type="abstract" xml:lang="en">The FEMAXI-IV code is an extension of the earlier version FEMAXI-III. The primary improvement in the new version is the provision for treating the fuel rod behavior during an operational transient. For this purpose, the time-dependent models are used for heat conduction, fission gas release, and mixing of the released gas with the plenum gas.In FEMAXI-IV, the fission gas release model was thoroughly revised from the previous version. It is based on the fission gas release model presented by White and Tucker. The model takes into account the following mechanisms: •- diffusion of gas atoms to the grain boundary;•- sweeping of gas atoms by grain growth;•- precipitation of gas atoms into intragranular gas bubbles;•- resolution of gas atoms from intragranular and grain boundary gas bubbles;•- fission gas release due to bubble interconnection.The model was incorporated into FEMAXI-IV and code calculations were compared with the fission gas release data obtained in the Inter-Ramp and Over-Ramp experiments.This paper describes the fission gas release model involved and results of calculations.</div></front></TEI><affiliations><list><country><li>Japon</li></country><region><li>Région de Kantō</li></region><settlement><li>Tokyo</li></settlement></list><tree><country name="Japon"><noRegion><name sortKey="Nakajima, T" sort="Nakajima, T" uniqKey="Nakajima T" first="T." last="Nakajima">T. Nakajima</name></noRegion><name sortKey="Saito, H" sort="Saito, H" uniqKey="Saito H" first="H." last="Saito">H. Saito</name></country></tree></affiliations></record>Pour manipuler ce document sous Unix (Dilib)
EXPLOR_STEP=$WICRI_ROOT/Eau/explor/LotaV3/Data/Main/Exploration
HfdSelect -h $EXPLOR_STEP/biblio.hfd -nk 001964 | SxmlIndent | more
Ou
HfdSelect -h $EXPLOR_AREA/Data/Main/Exploration/biblio.hfd -nk 001964 | SxmlIndent | more
Pour mettre un lien sur cette page dans le réseau Wicri
{{Explor lien
|wiki= Eau
|area= LotaV3
|flux= Main
|étape= Exploration
|type= RBID
|clé= ISTEX:D98B61C4CC7A234BC5DCF7FC162819A37D94FF28
|texte= A comparison between fission gas release data and FEMAXI-IV code calculations
}}
| This area was generated with Dilib version V0.6.39. |  |