TY - JOUR
T1 - Influence of corium oxidation on fission product release from molten pool
AU - Bechta, S.V.
AU - Krushinov, E.V.
AU - Vitol, S.A.
AU - Khabensky, V.B.
AU - Kotova, S.Yu.
AU - Sulatsky, A.A.
AU - Gusarov, V.V.
AU - Almyashev, V.I.
AU - Ducros, G.
AU - Journeau, C.
AU - Bottomley, D.
AU - Clément, B.
AU - Herranz, L.
AU - Guentay, S.
AU - Trambauer, K.
AU - Auvinen, Ari
AU - Bezlepkin, V.V.
PY - 2010
Y1 - 2010
N2 - 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.
AB - 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.
U2 - 10.1016/j.nucengdes.2010.01.008
DO - 10.1016/j.nucengdes.2010.01.008
M3 - Article
SN - 0029-5493
VL - 240
SP - 1229
EP - 1241
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
IS - 5
ER -