Title of article
Influence of corium oxidation on fission product release from molten pool Original Research Article
Author/Authors
S.V Bechta، نويسنده , , E.V Krushinov، نويسنده , , S.A Vitol، نويسنده , , V.B. Khabensky، نويسنده , , S.Yu. Kotova، نويسنده , , A.A Sulatsky، نويسنده , , V.V Gusarov، نويسنده , , V.I. Almyashev، نويسنده , , G. Ducros، نويسنده , , C. Journeau and G. Cognet ، نويسنده , , D. Bottomley، نويسنده , , B. Clement، نويسنده , , José L. Herranz، نويسنده , , S. Guentay، نويسنده , , K. Trambauer، نويسنده , , A. Auvinen، نويسنده , , V.V. Bezlepkin، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2010
Pages
13
From page
1229
To page
1241
Abstract
Qualitative and quantitative determination of the release of low-volatile fission products and core materials from molten oxidic corium was investigated in the EVAN project under the auspices of ISTC. The experiments carried out in a cold crucible with induction heating and RASPLAV test facility are described. The results are discussed in terms of reactor application; in particular, pool configuration, melt oxidation kinetics, critical influence of melt surface temperature and oxidation index on the fission product release rate, aerosol particle composition and size distribution. The relevance of measured high release of Sr from the molten pool for the reactor application is highlighted. Comparisons of the experimental data with those from the COLIMA CA-U3 test and the VERCORS tests, as well as with predictions from IVTANTHERMO and GEMINI/NUCLEA codes are made. Recommendations for further investigations are proposed following the major observations and discussions.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2010
Journal title
Nuclear Engineering and Design Eslah
Record number
895658
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