Monte Carlo capabilities of the SCALE code system
Creators
- 1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)
- 2. University of Tennessee, Knoxville, TN 37921 (United States)
Description
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. 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 that includes three deterministic and three Monte Carlo radiation transport solvers (KENO, MAVRIC, TSUNAMI) that can be selected based on the desired solution, including hybrid deterministic/Monte Carlo simulations. SCALE includes the latest nuclear data libraries for continuous-energy and multigroup radiation transport as well as activation, depletion, and decay calculations. SCALE's graphical user interfaces assist with accurate system modeling, visualization, and convenient access to desired results. SCALE 6.2, to be released in 2014, will provide several new capabilities and significant improvements in many existing features, especially with expanded continuous-energy Monte Carlo capabilities for criticality safety, shielding, depletion, and sensitivity and uncertainty analysis. An overview of the Monte Carlo capabilities of SCALE is provided here, with emphasis on new features for SCALE 6.2. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1051/snamc/201406007Additional details
Identifiers
Publishing Information
- Publisher
- EDP Sciences
- Imprint Place
- Les Ulis (France)
- Imprint Pagination
- (Suppl.) 13 p.
Conference
- Title
- SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
- Dates
- 27-31 Oct 2013
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 46007312
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BIOLOGICAL SHIELDING; COMPUTERIZED SIMULATION; CRITICALITY; K CODES; M CODES; MONTE CARLO METHOD; RADIATION TRANSPORT; S CODES; SENSITIVITY ANALYSIS; T CODES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; SHIELDING; SIMULATION
Optional Information
- Notes
- 33 refs.