ENDF/B-VII nuclear data libraries for SCALE 6

American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV

Volumn 2, Issue , 2009, Pages 764-771

  Williams, Mark L ^a   Ilas, Germina ^a  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CODE SYSTEM; CRITICAL EXPERIMENT; ENDF/B-VII; EXPERIMENTAL ERRORS; EXPERIMENTAL UNCERTAINTY; ISOTOPIC MEASUREMENT; LATTICE PHYSIC; MEASURED RESULTS; NUCLEAR DATA LIBRARY; SOURCE TERM ANALYSIS;

CURIUM; EUROPIUM; FISSION PRODUCTS; FUELS; GADOLINIUM; IONIC STRENGTH; ISOTOPES; LIBRARIES; NUCLEAR ENERGY; PLUTONIUM; SAMARIUM; SPENT FUELS; UNCERTAINTY ANALYSIS;

EXPERIMENTS;

EID: 74549138055     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (7)

1. SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, ORNL-TM/2005/39, Version 6, Vols. I-III, January 2009. (Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-750.)
2. M. B. CHADWICK et al., "ENDF/B-VII.0 Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology," Special Issue on Evaluated Nuclear Data File ENDF/B-VII.0 Nuclear Data Sheets, 107(12), 2931-3059 (December 2006).
3. M. E. DUNN, N. M. GREENE, "AMPX-2000: A Cross-Section Processing System for Generating Nuclear Data for Criticality Safety Applications," Trans. Am. Nucl. Soc., 86, 118, 2002.
4. S. GOLUOGLU, M. E. DUNN, L. M. PETRIE, and T. S. SUMNER, "Development and Validation of the New Continuous Energy Capability in the Criticality Safety Code KENO," in Proceedings of the International Conference on the Physics of Reactors (PHYSOR "08), Interlaken, Switzerland, September 14-19, 2008.
5. International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95) 03/I, Nuclear Energy Agency, Paris (September 2008 Edition).
6. D. BOULANGER et al., "High burnup PWR and BWR MOX fuel performance: a review of Belgonucleaire recent experimental programs," Proceedings of the International Meeting on LWR Fuel Performance, Orlando, Florida (2004).
7. G. ILAS and I. C. GAULD, "Analysis of Isotopic Assay Data from the MALIBU Program" CD Proceedings of PHYSOR 2008 (September 2008).