Published September 18, 1987
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RELAP 5 Simulations of a hypothetical LOCA in Ringhals 2
Description
RELAP5 simulations of a hypothetical LOCA in Ringhals 2 were conducted in order to determine the sensitivity of the calculated peak cladding temperature (PCT) to Appendix K requirements. The PCT was most sensitive to the assumed model decay heat: Changing from the 1979 ANS Standard to 1.2 times the 1973 Standard increased the PCT by 70 to 100K. After decay heat, the two parameters which affected the PCT the most were steam generator heat transfer and heat transfer lockout. The PCT was not sensitive to the assumed pump rotor condition (locked vs coasting); nor was it sensitive to a modest amount (5 to 10%) of steam generator tube plugging. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
20019277.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 71 p.
- Report number
- SKI--87089
INIS
- Country of Publication
- Sweden
- Country of Input or Organization
- Sweden
- INIS RN
- 20019277
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; ECCS; FUEL CANS; HEAT TRANSFER; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; RINGHALS-2 REACTOR; VERY HIGH TEMPERATURE
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Project SKI-13.3-991/85-87089
- Secondary number(s)
- STUDSVIK-NP--87-105.