Validation of ENDF/B-VI.2, JEF-2.2 and JENDL-3.2 through MCNP analysis of BWR-simulated critical experiments

Annals of Nuclear Energy

Volumn 24, Issue 3, 1997, Pages 197-204

  Kim, Jung Do ^a   Gil, Choong Sup ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

CALCULATIONS; COMPUTER SIMULATION; CRITICALITY (NUCLEAR FISSION); EIGENVALUES AND EIGENFUNCTIONS; EXPERIMENTS; LIGHT WATER REACTORS; MATRIX ALGEBRA; NUCLEAR FUELS; REACTOR CORES; TEMPERATURE;

ENERGY DATA; FISSION DENSITY DISTRIBUTION; NUCLEAR DATA;

BOILING WATER REACTORS;

EID: 0031077456     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/0306-4549(96)00039-4     Document Type: Article

References (3)

1. Briesmeister J. (Editor) (Nov. 1993) "MCNP-A General Monte Carlo Code N-Particle Transport Code Version 4A." LA-12625-M.
2. MacFarlane R.E. and Muir D.W. (Oct. 1994) "The NJOY Nuclear Data Processing System, Version 91." LA-12740-M.
3. Sitaraman S. and Rahnema F. (1993) "Criticality Analysis of Heterogeneous Light Water Reactor Configurations." Nucl. Sci. & Eng., 113, 239-250.