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Title: BWR plant analyzer development at BNL

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