Severe accident code development program
Description
This paper summarizes the scope and status of the Severe Accident Code Development Program, which is part of the NRC Severe Fuel Damage and Source Term (SFD/ST) Research Program. The Program consists of the development and assessment of the state-of-the-art mechanistic computer codes: SCDAP/RELAP5 and MELPROG/TRAC. The SCDAP/RELAP5 code has been developed to make detailed analysis of the SFD/ST experiments and also to analyze the progression of the TMI-type recovered accidents in the reactor coolant system (RCS) of nuclear power plants. The code is currently operational on a CRAY-I computer and was used successfully to make a pretest prediction for the LOFT FP-2 core damage test with the entire RCS modeled. THe MELPROG/TRAC code is being developed to analyze severe accident progression in the RCS up to and including vessel failure. Code assessment and improvement for both codes will continue in the near future
Additional details
Publishing Information
- Imprint Title
- Thirteenth water reactor safety research information meeting: proceedings. Volume 6
- Journal Page Range
- p. 339-346.
- Report number
- NUREG/CP--0072-Vol.6
Conference
- Title
- 13. water reactor safety research information meeting.
- Dates
- 22-25 Oct 1985.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18002589
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; CRAY COMPUTERS; FAILURES; FISSION PRODUCT RELEASE; LOFT REACTOR; M CODES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; RADIOACTIVITY TRANSPORT; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; S CODES; SEPARATION PROCESSES; T CODES
- Descriptors DEC
- ACCIDENTS; COMPUTERS; CONTAINERS; CONTAINMENT; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SIMULATION; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS