On the validation of release 3 of ENDF/B-VI nuclear data for light water reactor criticality analysis

Annals of Nuclear Energy

Volumn 24, Issue 14, 1997, Pages 1151-1155

  Rahnema, Farzad ^a   McKinley, Scott ^a  

^a GEORGIA INSTITUTE OF TECHNOLOGY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER AIDED ANALYSIS; COMPUTER SIMULATION; COMPUTER SOFTWARE; CRITICALITY (NUCLEAR FISSION); DATABASE SYSTEMS; EIGENVALUES AND EIGENFUNCTIONS; MONTE CARLO METHODS;

REACTOR CRITICALITY ANALYSIS; SOFTWARE PACKAGE MCNP;

LIGHT WATER REACTORS;

EID: 0031236458     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0306-4549(97)00036-4     Document Type: Article

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