SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4
Creators
- 1. Oak Ridge National Lab., TN (United States)
- 2. Lawrence Livermore National Lab., CA (United States)
Description
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
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI95012139; NTIS; GPO.Files
26074546.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 766 p.
- Report number
- NUREG/CR--0200-Vol.3-Rev.4
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26074546
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S42: ENGINEERING; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Computer Program Description
- Descriptors DEI
- BURNUP; CASKS; COMPUTER PROGRAM DOCUMENTATION; CRITICALITY; HEAT TRANSFER; LICENSING; MANUALS; NUCLEAR FACILITIES; NUCLEAR FUELS; S CODES; SAFETY ANALYSIS; SHIELDING; TRANSPORT
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; DOCUMENT TYPES; ENERGY SOURCES; ENERGY TRANSFER; FUELS; MATERIALS; REACTOR MATERIALS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- ORNL/NUREG/CSD--2/R4-Vol.3.