TRAC-BF1/NEM modeling and results of OECD/NEA BWR core transient benchmarks

Annals of Nuclear Energy

Volumn 27, Issue 12, 2000, Pages 1051-1058

  Fu, Haoying ^a   Solis Rodarte, Jorge ^a   Ivanov, Kostadin N ^a  

^a PENNSYLVANIA STATE UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BOILING WATER REACTORS; COMPUTER SIMULATION; MATHEMATICAL MODELS; NEUTRONS; NUCLEAR REACTOR ACCIDENTS; THERMAL EXPANSION; TRANSIENTS;

CORE TRANSIENT BENCHMARKS; NEUTRONICS THERMAL HYDRAULICS; TRAC-BF1 NEM MODELING;

REACTOR CORES;

EID: 0033750977     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(99)00111-5     Document Type: Article

References (7)

1. Bandini, B.R., 1990. A three-dimensional transient neutronics routine for the TRAC-PF1 reactor thermal-hydraulic computer code. Ph.D. thesis, The Pennsylvania State University.
2. Borkowski, J.A., Wade, N.L., 1992. TRAC-BF1/MOD1, an advanced best estimate computer program for BWR accident analysis. Idaho National Engineering Laboratory.
3. Finnemann, H., Bauer, H., Galati, A., Martinelli, R., 1993. Results of LWR core transient benchmarks. NEA/NSC/DOC(93)25.
4. Finnemann, H., Galati, A., 1992. NEACRP 3-D LWR core transient benchmark. Final specifications. NEACRP-L-335, Revision 1.
5. Kaloinen, E., Kyrki-Rajamaki, R., Raty, H., 1998. Calculation of BWR transients with the 3D dynamics code TRAB-3D. In: Proceedings of the International Reactor Physics Conference, Long Island, USA, Vol. 1, pp. 1444-1451.
6. Lu, S., 1997. GE simplified boiling water reactor stability analysis in time domain. Ph.D. thesis, The Pennsylvania State University.
7. Solis-Rodarte, J., 1998. Reactivity insertion accident analysis using TRAC-BF1/NEM: feedback testing and coupled code qualification. Ms thesis, The Pennsylvania State University.