RELAP5/MOD3 calculations for GIST data
- 1. Idaho National Engineering Lab., Idaho Falls, ID (United States)
- 2. Nuclear Regulatory Commission, Washington, DC (United States)
Description
An input deck for the thermal-hydraulic modeling code RELAP5/MOD3 was constructed to simulate the Gravity Driven Cooling System (GDCS) Integrated Systems Test (GIST) facility. The GIST facility was operated by General Electric at their site in San Jose, CA, as part of the GDCS test program. Capabilities and limitations of the database generated during the test program with respect to code assessment are discussed. Five calculations were performed with the RELAP5/MOD3 GIST model. The calculations include four loss-of-coolant accident calculations (LOCAs) and one feedwater trip calculation. The results of the calculations are presented, including a discussion of code errors found and corrected
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs
- Imprint Pagination
- 586 p.
- Journal Page Range
- p. 531-547.
- Report number
- NUREG/CP--0133-Vol.1
Conference
- Title
- 21. water reactor safety information meeting.
- Dates
- 25-27 Oct 1993.
- Place
- Bethesda, MD (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26033783
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; ECCS; GRAVITATION; R CODES; REACTOR ACCIDENTS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-931079--Vol.1.