Development and validation of the new continuous energy capability in the criticality safety code KENO

International Conference on the Physics of Reactors 2008, PHYSOR 08

Volumn 3, Issue , 2008, Pages 1732-1743

  Goluoglu, Sedat ^a   Dunn, Michael E ^a   Petrie, Lester M ^a   Sumner, Tyler S ^b  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b GEORGIA INSTITUTE OF TECHNOLOGY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BENCH-MARK PROBLEMS; CONTINUOUS ENERGY; CRITICALITY SAFETY; CROSS SECTION DATA; ENDF/B-VI; ENDF/B-VII; PROBLEM SETS; PROCESSING SYSTEMS;

CODES (SYMBOLS);

EID: 79953851463     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluations, ORNL/TM-2005/39, Version 5.1, Vols. I-III, November 2006. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-732.
2. Dunn, M.E., Greene, N.M. 2002. AMPX-2000: A Cross-Section Processing System for Generating Nuclear Data for Criticality Safety Applications. Trans. Am. Nucl. Soc. 86, 118-119.
3. Goluoglu, S., Dunn, M.E., Greene, N.M., Petrie, L.M., and Hollenbach, D.F. 2007. Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO, Proc. of ICNC 2007, St. Petersburg, Russia.
4. International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03, OECD-NEA, September, 2007.