TRAC-BF1/NEM Modeling and results of OECD/NEA BWR core transient benchmarks
Description
TRAC-BF1/NEM is a coupled neutronics-thermal hydraulics code for BWR transient and accident analysis developed at the Penn State University. Research has been carried out at Penn State to further verify this coupled code by using the (OECD/NEA) 3-D BWR core transient benchmarks. These benchmarks provide an opportunity to compare TRAC-BF1/NEM predictions with the results of many other coupled codes as well as to establish a well-defined set of test problems for future TRAC-BF1/NEM modifications and code distributions. The paper gives a description of the developed neutronics and thermal-hydraulic models and presents a comparison and discussion of the obtained steady-state results as well as the transient results for the inlet sub-cooling transient
Additional details
Identifiers
- PII
- S0306454999001115;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 27
- Journal Issue
- 12
- Journal Page Range
- p. 1051-1058
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33030114
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; BWR TYPE REACTORS; MATHEMATICAL MODELS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR KINETICS; REACTOR PHYSICS; RISK ASSESSMENT; STEADY-STATE CONDITIONS; SUBCOOLING; T CODES; THERMAL ANALYSIS; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING; ENRICHED URANIUM REACTORS; KINETICS; PHYSICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2000 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.