Published April 1992
| Version v1
Report
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Post-test analysis of LOBI test BT-12 using RELAP5/MOD2
Creators
- 1. UKAEA Atomic Energy Establishment, Winfrith (United Kingdom)
Description
This report describes calculations carried out with RELAP5/MOD2 on LOBI experiment BT-12, a large steam line break. The following sensitivity studies were performed: heat losses on the intact steam generator; discharge coefficient at break; water in steam lines; nearly implicit numerics. Qualitatively the general trends of BT-12 were predicted well, in particular the timing of events was fairly accurate
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI92014120; NTIS; INIS; GPO.
Files
Additional details
Publishing Information
- Imprint Pagination
- 63 p.
- Report number
- NUREG/IA--0079
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23067899
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTER CALCULATIONS; ENERGY LOSSES; HEAT TRANSFER; HYDRAULICS; INTERNATIONAL COOPERATION; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; REACTOR SAFETY; RESEARCH PROGRAMS; SENSITIVITY ANALYSIS; STEAM GENERATORS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; COOPERATION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- AEEW-R--2645.