Scale 6.1 Enhancements for Nuclear Criticality Safety

Conference · Mon Sep 19 04:00:00 EDT 2011

OSTI ID:1025851

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 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 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 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: 1025851
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
ALARM SYSTEMS
CRITICALITY
Criticality Safety, Reactor Physics, Radiation Shielding, and Sensitivity and Uncertainty Analysis: Tool Set
DESIGN
FLEXIBILITY
Nuclear Criticality Safety Program (NCSP)
ORNL
PERFORMANCE
RADIATION ACCIDENTS
RADIATION TRANSPORT
RADIATIONS
REACTOR PHYSICS
SAFETY
SAFETY ANALYSIS
SENSITIVITY
SHIELDING
SIMULATION
SOURCE TERMS
Scale 6.1
Scale Code System
TESTING
VERIFICATION