MELCOR 1.8.2 assessment: Surry PWR TMLB' (with a DCH study)
Description
MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC. This code models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs. As part of an ongoing assessment program, the MELCOR computer code has been used to analyze a station blackout transient in Surry, a three-loop Westinghouse PWR. Basecase results obtained with MELCOR 1.8.2 are presented, and compared to earlier results for the same transient calculated using MELCOR 1.8.1. The effects of new models added in MELCOR 1.8.2 (in particular, hydrodynamic interfacial momentum exchange, core debris radial relocation and core material eutectics, CORSOR-Booth fission product release, high-pressure melt ejection and direct containment heating) are investigated individually in sensitivity studies. The progress in reducing numeric effects in MELCOR 1.8.2, compared to MELCOR 1.8.1, is evaluated in both machine-dependency and time-step studies; some remaining sources of numeric dependencies (valve cycling, material relocation and hydrogen burn) are identified
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94008819; NTIS; US Govt. Printing Office Dep.Files
25047657.pdf
Files
(16.4 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 319 p.
- Report number
- SAND--93-1899
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25047657
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; M CODES; MATHEMATICAL MODELS; OUTAGES; REACTOR ACCIDENTS; SENSITIVITY ANALYSIS; SURRY-1 REACTOR; THEORETICAL DATA; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; EVALUATION; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-94AL85000
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).