Criticality safety enhancements for SCALE 6.2 and beyond - 14648

Conference · Tue Sep 15 04:00:00 EDT 2015

OSTI ID:23100975

Rearden, B. T.; Bekar, K. B.; Celik, C.; Clarno, K. T.; Dunn, M. E.; Hart, S. W. D.; Ibrahim, A. M.; Johnson, S. R.; Langley, B. R.; Lefebvre, J. P.; Lefebvre, R. A.; Marshall, W. J.; Mertyurek, U.; Mueller, D. E.; Peplow, D. E.; Perfetti, C. M.; Petrie, Jr., L. M.; Thompson, A. B.; Wiarda, D.; Wieselquist, W. A. ; Williams, M. A. ^[1]

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1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6170 (United States)

SCALE is a widely used suite of tools for nuclear systems modeling and simulation that provides comprehensive, verified and validated, user-friendly capabilities for criticality safety, reactor physics, radiation shielding, and sensitivity and uncertainty analysis. Since 1980, regulators, industry, and research institutions around the world have relied on SCALE for nuclear safety analysis and design. SCALE 6.2 provides several new capabilities and significant improvements in many existing features for criticality safety analysis. Enhancements are realized for nuclear data; multigroup resonance self-shielding; continuous-energy Monte Carlo analysis for sensitivity/uncertainty analysis, radiation shielding, and depletion; and graphical user interfaces. An overview of these capabilities is provided in this paper, and additional details are provided in several companion papers. (authors)

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 23100975
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
97 MATHEMATICS AND COMPUTING
CRITICALITY
DESIGN
GRAPHICAL USER INTERFACE
MONTE CARLO METHOD
REACTOR PHYSICS
REACTOR SAFETY
SAFETY ANALYSIS
SELF-SHIELDING
SENSITIVITY
SHIELDING
SIMULATION