Nakai, Ryodai 
; Suzuki, Toru; Kamiyama, Kenji 
; Seino, Hiroshi ; Koyama, Kazuya*; Morita, Koji*
The evaluation technology of Level-2 PSA for Sodium-Cooled Fast Reactors (SFRs) was established in order to systematically assess the core damage sequences. In addition to the existing computational tools for Level-2 PSA, the computational tools, MUTRAN and SIMMER-LT were developed for core material relocation phase. Also the analytical models, CORCON and VANESA, were improved based on newly performed experiments for the ex-vessel phase taking into account the feature of SFRs. The technical information was compiled as technical database used in the construction and quantification of level-2 PSA event trees for SFRs. The technical basis was established for the Level-2 PSA for SFRs.
Language |
: | English |
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Number |
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Pages |
: | 12 Pages |
Publication Year/Month |
: | 2010/10 |
Meeting title |
: | 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8) |
Held date |
: | 2010/10 |
Location (city) |
: | Shanghai |
Location (country) |
: | China |
Paper URL |
: |
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Keywords |
: | no keyword |
Article of JAEA R&D Review |
: | Safety Evaluation of Core Disruptive Accidents; Development of Level-2 PSA Methodology for FBRs[ |
Cooperating Institute |
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