Development of a three-dimensional CDA analysis code: SIMMER-IV and its first application to reactor case

For the transition phase analysis of core disruptive accidents, the development of a three-dimensional reactor safety analysis code, SIMMER-IV, has been carried out based on the technology of the two-dimensional SIMMER-III code. The world first application of SIMMER-IV to a small-sized sodium-cooled...

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Bibliographic Details
Published in:Nuclear engineering and design 2008, Vol.238 (1), p.66-73
Main Authors: Yamano, Hidemasa, Fujita, Satoshi, Tobita, Yoshiharu, Sato, Ikken, Niwa, Hajime
Format: Article
Language:English
Subjects:
Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Fuels
Installations for energy generation and conversion: thermal and electrical energy
Nuclear fuels
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Summary:For the transition phase analysis of core disruptive accidents, the development of a three-dimensional reactor safety analysis code, SIMMER-IV, has been carried out based on the technology of the two-dimensional SIMMER-III code. The world first application of SIMMER-IV to a small-sized sodium-cooled fast reactor has also been attempted to clarify event progression in the early stage of the transition phase. This SIMMER-IV calculation is compared to the two-dimensional case calculated by SIMMER-III, neglecting the presence of control rod guide tubes. The present analysis with the three-dimensional representation suggests that the conventional scenario leading to rather early high-mobility fuel pool formation is unrealistic and the degraded core tends to keep low mobility in the early stage of transition phase.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2007.04.015