Enhancements in SCALE 6.1
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:993018
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
The Standardized Computer Analysis for Licensing Evaluation (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 nearly 80 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, scheduled for release in the fall of 2010, provides improved reliability and introduces a number of enhanced features, some of which are briefly described here. SCALE 6.1 provides state-of-the-art capabilities for criticality safety, reactor physics, and radiation shielding in a robust yet user-friendly package. The new features and improved reliability of this latest release of SCALE are intended to improve safety and efficiency throughout the nuclear community.
- 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:
- 993018
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 103
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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97 MATHEMATICS AND COMPUTING
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CRITICALITY
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EFFICIENCY
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Nuclear Criticality Safety Program (NCSP)
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97 MATHEMATICS AND COMPUTING
COMPUTERS
CRITICALITY
DESIGN
EFFICIENCY
EVALUATION
LICENSING
Nuclear Criticality Safety Program (NCSP)
ORNL
RADIATION TRANSPORT
RADIATIONS
REACTOR PHYSICS
RELIABILITY
SAFETY
SAFETY ANALYSIS
SENSITIVITY
SHIELDING
SIMULATION
Standardized Computer Analysis for Licensing Evaluation (SCALE) Code System