Features and performance of a coupled three-dimensional thermal-hydraulic/kinetics TRAC-PF1/NEM pressurized water reactor (PWR) analysis code

Annals of Nuclear Energy

Volumn 26, Issue 15, 1999, Pages 1407-1417

  Ivanov, Kostadin N ^a   Macian Juan, Rafael ^b   Irani, Adi ^c   Baratta, Anthony J ^a  

^a PENNSYLVANIA STATE UNIVERSITY   (United States)

^b PAUL SCHERRER INSTITUTE   (Switzerland)

^c First Energy Corporation   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER AIDED ANALYSIS; COMPUTER SIMULATION; COMPUTER SOFTWARE; REACTIVITY (NUCLEAR); THREE DIMENSIONAL COMPUTER GRAPHICS; TRANSIENTS;

REACTIVITY INSERTION ACCIDENT; SOFTWARE PACKAGE TRAC-PF1/NEM;

PRESSURIZED WATER REACTORS;

EID: 0033212249     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(99)00017-1     Document Type: Article

References (9)

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2. Edenius, M., Forssen, B., 1989. CASMO-3 - A Fuel Assembly Burnup Program. User's Manual, STUDSVIK/NFA-89/3.
3. Ivanov, K.N., Baratta, A.J., Bandini, B.R., 1995a. Three-dimensional NEM/TRAC-PF1 Rod Ejection Benchmark Analyses. TANSAO 72, 343.
4. Ivanov, K.N. et al. 1995b. TMI MSLB Analysis Using TRAC-PF1 Coupled with Three-dimensional Kinetics, TANSAO 73, 246.
5. Ivanov K.N., Baratta A.J. Recent improvements to the coupled TRAC-PF1/NEM methodology. TANSAO. 75:1996;329.
6. Macian-Juan R., Ivanov K.N., Mahaffy J.H. Numerical diffusion and the tracking of solute fields in systems codes. Nuclear Engineering and Design. 179(3):1998;321.
7. Schnurr, N.M. et al., 1992. TRAC-PF1/MOD2: Volume 1. Theory Manual, Los Alamos National Laboratory Report LA-12031-M, Vol. I, NUREG/CR-5673.
8. SIMULATE-3 User's Manual, 1992. An Advanced Three-Dimensional Two-Group Reactor Analysis Code, STUDSVIK/SOA-92/01.
9. Tyler, T.N., Macian-Juan, R., Mahaffy, J.H. 1995. Analysis of the Return to Power Scenario Following a LBLOCA in a PWR, In: Proceedings of NURETH-7, Saratoga Springs.