BWR plant analyzer development at BNL

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:5900118

Cheng, H S; Wulff, W; Mallen, A N; Lekach, S V; Stritar, A; Cerbone, R J

Advanced technology for high-speed interactive nuclear power plant simulations is of great value for timely resolution of safety issues, for plant monitoring, and for computer-aided emergency responses to an accident. Presented is the methodology employed at BNL to develop a BWR plant analyzer capable of simulating severe plant transients at much faster than real-time process speeds. Five modeling principles are established and a criterion is given for selecting numerical procedures and efficient computers to achieve the very high simulation speeds. Typical results are shown to demonstrate the modeling fidelity of the BWR plant analyzer.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5900118
• Report Number(s): BNL-NUREG-35843; CONF-850411-10; ON: TI85007280; TRN: 85-006394
• Resource Relation: Conference: International meeting on advances in nuclear engineering computational methods, Knoxville, TN, USA, 9 Apr 1985
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
SYSTEMS ANALYSIS
COMPUTERIZED SIMULATION
BNL
COMPUTER CODES
MATHEMATICAL MODELS
NUCLEAR POWER PLANTS
ACCIDENTS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
POWER PLANTS
REACTORS
SAFETY
SIMULATION
THERMAL POWER PLANTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled