Station blackout simulation model for a BWR plant
- 1. Univ. of Illinois, Urbana (United States)
Description
This paper presents the results of a station blackout transient analysis for the Hope Creek boiling water reactor (BWR). The analysis has been performed using the MOD2 version of the best-estimate code RELAP5 on a Cyber 932 under the NOS/VE operating system. Whereas the RELAP5 code is primary a pressurized water reactor simulation code, new modeling features introduced into the MOD2 version, particularly the jet-mixer model, has allowed the authors to effectively simulate the jet pumps in BWR systems. The station blackout transient, unless otherwise stated, assumes and takes credit for normal functioning of plant instrumentation and controls, plant protection, and reactor protection system. In their analysis, three cases with different plant states and protection availabilities have been considered: (1) reference case: no steam dump, three banks of S/R valves available, the reactor coolant inventory control (RCIC) and high pressure core injection (HPCI) systems not operative; (2) steam dump: 25% steam dump, three banks of S/R valves available, the RCIC and HPCI systems not operative; and (3) HPCI system on: no steam dump, three banks of S/R valves available, the HPCI and HPCS systems operative
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Journal Page Range
- p. 362-364.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-16 Nov 1990.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038777
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AC SYSTEMS; BYPASSES; COMPUTER CODES; COMPUTERIZED SIMULATION; CORE SPRAY SYSTEMS; ECCS; HEAT TRANSFER; HIGH PRESSURE COOLANT INJECTIO; HOPE CREEK-1 REACTOR; HYDRAULICS; LOW PRESSURE COOLANT INJECTION; OUTAGES; PERFORMANCE TESTING; PRESSURE SUPPRESSION; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PROBABILITY; PUMPS; QUALITY ASSURANCE; R CODES; REACTOR CONTROL SYSTEMS; REACTOR CORES; REACTOR INSTRUMENTATION; REACTOR OPERATION; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REGULATIONS; TIME DEPENDENCE; TRANSIENTS; US NRC
- Descriptors DEC
- BWR TYPE REACTORS; CONTAINERS; CONTROL SYSTEMS; COOLING SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; LAWS; NATIONAL ORGANIZATIONS; OPERATION; POWER REACTORS; POWER SYSTEMS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION; TESTING; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.