Comparative Studies of ENDF/B-6.8, JEF-2.2 and JENDL-3.2 Data Libraries by Monte Carlo Modeling of High Temperature Reactors on Plutonium Based Fuel Cycles

Journal of Nuclear Science and Technology

Volumn 41, Issue 12, 2004, Pages 1228-1236

  Talamo, Alberto ^a   Gudowski, Waclaw ^a   Cetnar, Jerzy ^b  

^a ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

^b AGH UNIVERSITY OF SCIENCE AND TECHNOLOGY   (Poland)

Author keywords

Burnup; ENDF B; Gas cooled; Graphite moderated; GT MHR; JEF; JENDL; Plutonium; TRISO

Indexed keywords

COMPUTER SIMULATION; GAS TURBINES; ISOTOPES; NUMERICAL ANALYSIS; PLUTONIUM; RADIOACTIVE WASTES; RANDOM PROCESSES; REACTOR REFUELING; VECTORS;

BURNUP; ENDF/B; GAS-COOLED; GRAPHITE-MODERATED; GT-MHR; JEF; JENDL; MODULAR HELIUM REACTORS (MHR); TRISCO;

LIGHT WATER REACTORS;

EID: 13244277620     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2004.9726352     Document Type: Article

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