Published February 1986 | Version v1
Report Metadata-only

Overview of TRAC-BWR assessment: TRAC-BD1/MOD1 and TRAC-BF1

Creators

  • 1. EG and G Idaho, Inc., Idaho Falls

Description

The assessments of the TRAC-BWR code performed during FY-1984 and FY-1985 have been analyzed. The TRAC-BD1/MOD1 and TRAC-BF1 versions of the code were used in the assessments. The overall predictive quality of the code versions was evaluated and user guidelines for the TRAC-BD1/MOD1 code were generated. Results of the analysis indicate that most deviations between code simulations and experimental data were more related to modeling practice than to code technology deficiencies. The analysis showed TRAC-BF1 was approximately 60% faster in execution than was TRAC-BD1/MOD1 while maintaining the same general quality of simulation

Additional details

Publishing Information

Imprint Title
Thirteenth water reactor safety research information meeting: proceedings. Volume 5
Journal Page Range
p. 357-366.
Report number
NUREG/CP--0072-Vol.5

Conference

Title
13. water reactor safety research information meeting.
Dates
22-25 Oct 1985.
Place
Gaithersburg, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18002567
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BROWNS FERRY-3 REACTOR; BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; EFFICIENCY; FLOW MODELS; HEAT TRANSFER; HYDRAULICS; IDAHO NATIONAL ENGINEERING LAB; LOSS OF COOLANT; REACTOR ACCIDENTS; REACTOR SAFETY; RELIEF VALVES; T CODES; TESTING; TRANSIENTS; US NRC
Descriptors DEC
ACCIDENTS; CONTAINMENT; CONTROL EQUIPMENT; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; MATHEMATICAL MODELS; MIXED SPECTRUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; US DOE; US ERDA; US ORGANIZATIONS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS