SCALE Code System 6.2.1

Technical Report · Mon Aug 01 00:00:00 EDT 2016

DOI:https://doi.org/10.2172/1326509· OSTI ID:1326509

Rearden, Bradley T. ^[1]; Jessee, Matthew Anderson ^[1]

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

The SCALE Code System is a widely-used modeling and simulation suite for nuclear safety analysis and design that is developed, maintained, tested, and managed by the Reactor and Nuclear Systems Division (RNSD) of Oak Ridge National Laboratory (ORNL). SCALE provides a comprehensive, verified and validated, user-friendly tool set for criticality safety, reactor and lattice physics, radiation shielding, spent fuel and radioactive source term characterization, and sensitivity and uncertainty analysis. Since 1980, regulators, licensees, and research institutions around the world have used SCALE for safety analysis and design. SCALE provides an integrated framework with dozens of computational modules including three deterministic and three Monte Carlo radiation transport solvers that are selected based on the desired solution strategy. SCALE includes current nuclear data libraries and problem-dependent processing tools for continuous-energy (CE) and multigroup (MG) neutronics and coupled neutron-gamma calculations, as well as activation, depletion, and decay calculations. SCALE includes unique capabilities for automated variance reduction for shielding calculations, as well as sensitivity and uncertainty analysis. SCALE’s graphical user interfaces assist with accurate system modeling, visualization of nuclear data, and convenient access to desired results.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1326509
• Report Number(s): ORNL/TM-2005/39 Version 6.2.1; TRN: US1700293
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
S CODES
REACTOR SAFETY
SAFETY ANALYSIS
ORNL
NEUTRONS
GAMMA RADIATION
SPENT FUELS
MONTE CARLO METHOD
COMPUTERIZED SIMULATION
DESIGN
SENSITIVITY ANALYSIS
SHIELDING
MATHEMATICAL SOLUTIONS
DATA COVARIANCES
SOURCE TERMS
RADIATION TRANSPORT
CRITICALITY
DECAY
DISPLAY DEVICES
MULTIGROUP THEORY
DATA VISUALIZATION
REACTOR LATTICES
REACTOR PHYSICS