Station blackout simulation model for a BWR plant
- Univ. of Illinois, Urbana (United States)
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.
- OSTI ID:
- 6932254
- Report Number(s):
- CONF-901101--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 62; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
AC SYSTEMS
BLACKOUTS
BWR TYPE REACTORS
BYPASSES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
CONTROL SYSTEMS
COOLING SYSTEMS
CORE SPRAY SYSTEMS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HOPE CREEK-1 REACTOR
HYDRAULICS
LOW PRESSURE COOLANT INJECTION
MECHANICS
NATIONAL ORGANIZATIONS
OPERATION
PERFORMANCE TESTING
POWER REACTORS
POWER SYSTEMS
PRESSURE SUPPRESSION
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PROBABILITY
PUMPS
QUALITY ASSURANCE
R CODES
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
REGULATIONS
SAFETY
SIMULATION
SPARGERS
TESTING
THERMAL REACTORS
TIME DEPENDENCE
TRANSIENTS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS