Subcooled decompression analysis of the ROSA and the LOFT semiscale blowdown test data with the digital computer code DEPCO-MULTI
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
In the ROSA (Rig of Safety Assessment) program, the digital computer code DEPCO-SINGLE and DEPCO-MULTI (Subcooled Decompression Process in Loss-of-Coolant Accident - Single Pipe and - Multiple Pipe Network) were prepared to study thermo-hydraulic behavior of the primary coolant in subcooled decompression of the PWR LOCA. The analytical results with DEPCO-MULTI on the subcooled decompression phenomena are presented for ROSA-I, ROSA-II and LOFT 500, 600, 700 and 800 series experiments. The effects of space mesh length, elasticity of pressure boundary materials and simplification for computational piping system on the computed result are described. This will be the final work on the study of the subcooled decompression analysis as for the ROSA program, and the authors wish that the present code shall further be examined with the data of much advanced experiments. (auth.)
Availability note (English)
MF available from INIS under the Report Number.Files
8301809.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 31 p.
- Report number
- JAERI-M--6340
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 8301809
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BLOWDOWN; COMPARATIVE EVALUATIONS; D CODES; ELASTICITY; HIGH PRESSURE; HYDRODYNAMICS; LOFT REACTOR; PRESSURE SUPPRESSION; PWR TYPE REACTORS; REACTOR SAFETY; SAFETY ENGINEERING; SPECIFICATIONS; SUBCOOLING; THERMODYNAMICS; TIME DEPENDENCE
- Descriptors DEC
- COMPUTER CODES; COOLING; FLUID MECHANICS; MECHANICAL PROPERTIES; MECHANICS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TANK TYPE REACTORS; TENSILE PROPERTIES; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS