Published March 1990
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An investigation of steam-explosion loadings with SIMMER-2
Description
The purpose of this work was to provide a reasonable estimate of the maximum loads that might be expected at the upper head of a pressurized water reactor following an in-vessel steam explosion. These loads were determined by parametric cases using a specially modified and calibrated version of the SIMMER-II computer code. Using the determined range of loads, the alpha-mode containment failure probability was to be estimated using engineering judgment. In this context, an alpha-mode failure is defined as resulting from a missile, produced by a steam explosion, and assuming core melt has occurred. 51 refs., 185 figs., 19 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A21/MF A01 as DE90009219; OSTI; INIS; US Govt. Printing Office Dep.Files
21054184.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 488 p.
- Report number
- LA--10639-MS
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21054184
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPILED DATA; COMPUTERIZED SIMULATION; CONTAINMENT; CORIUM; DATA COVARIANCES; EXPANSION; EXPLOSIONS; FAILURE MODE ANALYSIS; FUEL ELEMENTS; HEAT TRANSFER; HYDRODYNAMICS; LMFBR TYPE REACTORS; LOSS OF FLOW; M CODES; MELTDOWN; PROBABILITY; PWR TYPE REACTORS; REACTOR CORES; REACTOR SAFETY; REACTOR VESSELS; RISK ASSESSMENT; S CODES; STEAM; T CODES; THERMODYNAMICS; TWO-PHASE FLOW; VAPORS; WATER
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; CONTAINERS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EVALUATION; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; FLUID MECHANICS; FLUIDS; GASES; HYDROGEN COMPOUNDS; INFORMATION; LIQUID METAL COOLED REACTORS; MECHANICS; NUMERICAL DATA; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SOLVENTS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-7405-ENG-36