Criticality safety enhancements for SCALE 6.2 and beyond

Conference · Tue Sep 01 00:00:00 EDT 2015

OSTI ID:1225422

Rearden, Bradley T. ^[1]; Bekar, Kursat B. ^[1]; Celik, Cihangir ^[1]; Clarno, Kevin T. ^[1]; Dunn, Michael E. ^[1]; Hart, Shane W. ^[1]; Ibrahim, Ahmad M. ^[1]; Johnson, Seth R. ^[1]; Langley, Brandon R. ^[1]; Lefebvre, Jordan P. ^[1]; Lefebvre, Robert A. ^[1]; Marshall, William J. ^[1]; Mertyurek, Ugur ^[1]; Mueller, Don ^[1]; Peplow, Douglas E. ^[1]; Perfetti, Christopher M. ^[1]; Petrie Jr, Lester M. ^[1]; Thompson, Adam B. ^[1]; Wiarda, Dorothea ^[1]; Wieselquist, William A. ^[1] ; Williams, Mark L. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1225422
• Resource Relation: Conference: ICNC 2015, Charlotte, NC (United States), 13-17 Sep 2015
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICS AND COMPUTING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR SAFETY
SAFETY ANALYSIS
CRITICALITY
MONTE CARLO METHOD
S CODES
REACTOR PHYSICS
SENSITIVITY ANALYSIS
SHIELDING
COMPUTERIZED SIMULATION
RADIATION PROTECTION
DESIGN
MULTIGROUP THEORY
DISPLAY DEVICES
RESONANCE
SELF-SHIELDING