SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4
- Oak Ridge National Lab., TN (United States)
SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice; (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System developments has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3--for the data libraries and subroutine libraries.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Industrial and Medical Nuclear Safety; Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 72990
- Report Number(s):
- NUREG/CR-0200-Vol.3-Rev.4; ORNL/NUREG/CSD-2/R4-Vol.3; ON: TI95012139; TRN: 95:016267
- Resource Relation:
- Other Information: PBD: Apr 1995
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES
05 NUCLEAR FUELS
NUCLEAR FACILITIES
S CODES
LICENSING
CASKS
COMPUTER PROGRAM DOCUMENTATION
NUCLEAR FUELS
TRANSPORT
SHIELDING
HEAT TRANSFER
CRITICALITY
SAFETY ANALYSIS
MANUALS
BURNUP