会议专题

COMPASS Code Development: Validation of Multi-physics Analysis using Particle Method for Core Disruptive Accidents in Sodium-cooled Fast Reactors

Sodium-cooled fast reactors (SFRs) have been developed for efficient utilization of nuclear resources and reduction of environmental burden. In hypothetical core disruptive accidents (CDAs), recriticality should be avoided, for example, by molten fuel relocation. Mechanical energy release by recriticality is more serious when the size of the reactor core increases. For CDA analysis, we need to solve complex multi-physics problems involving molten core behavior, boiling of the coolant, failure of the structure, etc. A project for 5 years started in FY2005 for developing a code to analyze detailed processes of multi-phase multi-component thermal hydraulics and structural behavior in SFR CDAs. The code is named COMPASS. A particle method (Moving Particle Semi-implicit, MPS) is employed. In this paper, FY2009 results of the COMPASS code development are reported. Validation calculations for melt freezing and blockage formation, eutectic reaction of metal fuel, duct wall failure (thermal-hydraulic analysis), fuel pin failure and disruption and duct wall failure (structural analysis) are shown. Phase diagram calculations, classical and first-principles molecular dynamics were used to investigate physical properties of eutectic reactions: metallic fuel/steel and control rod material/steel. Basic studies for the particle method and SIMMER code calculations supported the COMPASS code development. COMPASS is expected to clarify the basis of experimentally-obtained correlations used in SIMMER. Combination of SIMMER and COMPASS will be useful for safety assessment of CDAs as well as optimization of the core design.

Sodium-cooled Fast Reactor Core Disruptive Accidents Particle Method Code Validation COMPASS SIMMER

S. Koshizuka Y. Uehara F. Inoue Y. Nagamine H. Yugo Y. Yamamoto M. Himi E. Hirano S. Shimizu M. Oue K. Morita T. Arima Y. Tobita H. Yamano T. Ito M. Naitoh N. Shirakawa H. Okada

Dept. Systems Innovation, Graduate School of Engineering, The University of Tokyo 7-3-1, Hongo Bunky The Institute of Applied Energy Japan Systems Corporation Kyushu University Japan Atomic Energy Agency Toyohashi University of Technology

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

1150-1160

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)