Welcome to SCALE
SCALE is a comprehensive modeling and simulation suite for nuclear safety analysis and design developed and maintained by Oak Ridge National Laboratory under contract with the U.S. Nuclear Regulatory Commission, U.S. Department of Energy, and the National Nuclear Security Administration to perform reactor physics, criticality safety, radiation shielding, and spent fuel characterization for nuclear facilities and transportation/storage package designs.
SCALE 6.2 is Now Available!
SCALE 6.2 represents one of the most comprehensive revisions in the history of SCALE, providing several new capabilities and significant improvements in many existing features.
New capabilities include
- evaluated nuclear data file (ENDF)/B-VII.1 nuclear data libraries—continuous energy (CE) and multigroup (MG) with enhanced group structures,
- neutron covariance data based on ENDF/B-VII.1 and supplemented with ORNL data,
- covariance data for fission product yields and decay constants,
- stochastic uncertainty and correlation quantification for any SCALE sequence with Sampler,
- parallel calculations with KENO,
- problem-dependent temperature corrections for CE calculations,
- CE shielding and criticality accident alarm system analysis with MAVRIC,
- CE Monte Carlo depletion with TRITON,
- CE sensitivity/uncertainty analysis with TSUNAMI-3D,
- simplified and efficient light water reactor (LWR) lattice physics with Polaris,
- large-scale detailed spent fuel characterization with ORIGAMI and ORIGAMI Automator,
- advanced fission source convergence acceleration capabilities with Sourcerer,
- nuclear data library generation with AMPX, and
- integrated user interface with Fulcrum.
Enhanced capabilities include
- accurate and efficient CE Monte Carlo methods for eigenvalue and fixed source calculations;
- Improved MG resonance self-shielding methodologies and data;
- resonance self-shielding with modernized and efficient XSProc integrated into most sequences;
- accelerated calculations with TRITON (generally 4x faster than SCALE 6.1);
- spent fuel characterization with 1470 pre-generated burnup libraries representing 61 reactor fuel types for use in ORIGEN and ORIGAMI;
- modernization of ORIGEN (Chebyshev Rational Approximation Method [CRAM] solver, API for high-performance depletion, new keyword input format);
- extension of the maximum mixture number to values well beyond the previous limit of 2147 to ~2 billion;
- nuclear data formats enabling the use of more than 999 energy groups;
- updated standard composition library to provide more accurate use of natural abundances; and
- numerous other enhancements for improved usability and stability.
The user documentation for SCALE has also been substantially updated and reorganized. More details are available in the newsletter, and updated training courses are scheduled.