SIMMER-III structure model. Model and method description
Creators
- 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center, Advanced Technology Division, Nuclear System Safety Research Group
- 2. Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan). Office of Planning and Arrangement for New Organization
Description
An advanced safety analysis code, SIMMER-III has been developed to evaluate the consequence of postulated core disruptive accidents of liquid-metal fast reactors (LMFRs). The present report describes a structure model for SIMMER-III to analyze a disrupting core. The structure in SIMMER-III, consisting of fuel pins and subassembly can walls, is modeled to exchange heat and mass with multiphase multicomponent flow of disrupted core material and to provide flow channel for fluids. In addition, complex behavior is modeled which changes configurations of structures as a result of heat and mass transfer from molten core materials. The structure model described in the present report alleviates some of limitations in the previous code SIMMER-II, and hence it is expected that the future researches with SIMMER-III will significantly improve the reliability and accuracy of LMFR safety analysis. (author)
Availability note (English)
Available from JST Library (JST: Japan Science and Technology Agency), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781 (domestic), FAX:+81-3-3979-2210 (oversea)Additional details
Publishing Information
- Imprint Pagination
- 92 p.
- Report number
- JNC-TN--9400-2004-043
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36045646
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CORIUM; FUEL CANS; FUEL ELEMENT FAILURE; FUEL PINS; HEAT TRANSFER; LMFBR TYPE REACTORS; MASS TRANSFER; MELTING; REACTOR CORE DISRUPTION; REACTOR SAFETY; S CODES; SAFETY ANALYSIS; WALLS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; ENERGY TRANSFER; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY