Enhancements in SCALE 6.1

Conference · Fri Apr 20 04:00:00 EDT 2012

OSTI ID:1039607

Rearden, Bradley T. ^[1]; Petrie, Jr, Lester M. ^[1]; Peplow, Douglas E. ^[1]; Jessee, Matthew Anderson ^[1]; Wiarda, Dorothea ^[1]; Williams, Mark L. ^[1]; Lefebvre, Robert A. ^[1]; Lefebvre, Jordan P. ^[1]; Gauld, Ian C. ^[1]; Goluoglu, Sedat ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The SCALE code system developed at Oak Ridge National Laboratory provides a comprehensive, verified and validated, user-friendly tool set for criticality safety, reactor physics, radiation shielding, and sensitivity and uncertainty analysis. For more than 30 years, regulators, licensees, and research institutions around the world have used SCALE for nuclear safety analysis and design. SCALE provides a 'plug-and-play' framework with 89 computational modules, including three deterministic and three Monte Carlo radiation transport solvers that are selected based on the desired solution. SCALE's graphical user interfaces assist with accurate system modeling, visualization, and convenient access to desired results. SCALE 6.1 builds on the existing capabilities and ease-of-use of SCALE and provides several new features such as enhanced lattice physics capabilities and multigroup Monte Carlo depletion, improved options and capabilities for sensitivity and uncertainty analysis calculations, improved flexibility in shielding and criticality accident alarm system calculations with automated variance reduction, and new options for the definition of group structures for depletion calculations. The SCALE 6.1 development team has focused on improved robustness via substantial additional regression testing and verification for new and existing features, providing improved performance relative to SCALE 6.0, especially in reactor physics calculations and in the nuclear data used for source term characterization and shielding calculations.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1039607
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
ALARM SYSTEMS
CRITICALITY
DESIGN
FLEXIBILITY
Improvements
Nuclear Criticality Safety Program (NCSP)
Nuclear Data
ORNL
PERFORMANCE
PHYSICS
RADIATION ACCIDENTS
RADIATION PROTECTION
RADIATION TRANSPORT
RADIATIONS
REACTOR PHYSICS
SAFETY
SCALE Code System
SENSITIVITY
SHIELDING
SIMULATION
SOURCE TERMS
Shielding Calculations
Source Term Characterization
TESTING
User-Friendly Tool Set
VERIFICATION