Title of article :
SIMMER-III applications to fuel–coolant interactions Original Research Article
Author/Authors :
K. Morita، نويسنده , , Sa. Kondo، نويسنده , , Y. Tobita، نويسنده , , D.J. Brear، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 1999
Pages :
21
From page :
337
To page :
357
Abstract :
The main purpose of the fast reactor safety analysis code, SIMMER-III, is to provide a numerical simulation of complex multiphase, multicomponent flow problems essential to investigate core disruptive accidents in liquid-metal fast reactors (LMFRs). However, the code is designed to be sufficiently flexible to be applied to a variety of multiphase flows, in addition to LMFR safety issues. In the present study, some typical experiments relating to fuel–coolant interactions (FCIs) have been analyzed by SIMMER-III to demonstrate that the code is applicable to such complex and highly transient multiphase flow situations. It is shown that SIMMER-III can reproduce the premixing phase both in water and sodium systems as well as the propagation of steam explosion. It is thus demonstrated the code is basically capable of simulating integral multiphase thermal-hydraulic problems included in FCI experiments.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
1999
Journal title :
Nuclear Engineering and Design Eslah
Record number :
888728
Link To Document :
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