Published June 2001
| Version v1
Journal article
Development and validation of sodium fire analysis code ASSCOPS
Creators
- 1. Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center
- 2. Inspection Development Company, Tokai, Ibaraki (Japan)
Description
A version 2.1 of the ASSCOPS sodium fire analysis code was developed to evaluate the thermal consequences of a sodium leak and consequent fire in LMFBRs. This report describes the computational models and the validation studies using the code. The ASSCOPS calculates sodium droplet and pool fire, and consequential heat/mass transfer behavior. Analyses of sodium pool or spray fire experiments confirmed that this code and parameters used in the validation studies gave valid results on the thermal consequences of sodium leaks and fires. (author)
Additional details
Publishing Information
- Journal Title
- Saikuru Kiko Giho
- Journal Issue
- no.11
- Journal Page Range
- p. 93-104
- ISSN
- 1344-4239
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 33008489
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; AEROSOLS; ANALYTICAL SOLUTION; BUILDINGS; BURNS; COMBUSTION; FIRES; LEAKS; LMFBR TYPE REACTORS; SAFETY; SODIUM; SPRAYS; TEMPERATURE DEPENDENCE; THERMODYNAMICS; TIME DEPENDENCE; VERIFICATION
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; CHEMICAL REACTIONS; COLLOIDS; COMPUTER CODES; DISEASES; DISPERSIONS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INJURIES; LIQUID METAL COOLED REACTORS; METALS; OXIDATION; REACTORS; SOLS; THERMOCHEMICAL PROCESSES
Optional Information
- Notes
- 19 refs., 11 figs., 2 tabs.