Typical BWR/4 MSIV closure ATWS analysis using RAMONA-3B code with space-time neutron kinetics

Conference · Sun Jan 01 04:00:00 EST 1984

OSTI ID:6475458

Neymotin, L; Saha, P

A best-estimate analysis of a typical BWR/4 MSIV closure ATWS has been performed using the RAMONA-3B code with three-dimensional neutron kinetics. All safety features, namely, the safety and relief valves, recirculation pump trip, high pressure safety injections and the standby liquid control system (boron injection), were assumed to work as designed. No other operator action was assumed. The results show a strong spatial dependence of reactor power during the transient. After the initial peak of pressure and reactor power, the reactor vessel pressure oscillated between the relief valve set points, and the reactor power oscillated between 20 to 50% of the steady state power until the hot shutdown condition was reached at approximately 1400 seconds. The suppression pool bulk water temperature at this time was predicted to be approx. 96/sup 0/C (205/sup 0/F). In view of code performance and reasonable computer running time, the RAMONA-3B code is recommended for further best-estimate analyses of ATWS-type events in BWRs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6475458
• Report Number(s): BNL-NUREG-35195; CONF-841075-3; ON: TI85000573
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
KINETICS
OSCILLATIONS
POWER
PRESSURE GRADIENTS
R CODES
REACTOR ACCIDENTS
REACTOR KINETICS
REACTOR PROTECTION SYSTEMS
REACTOR SHUTDOWN
REACTORS
SHUTDOWNS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS