Published April 1995 | Version v1
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SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F9--F16 -- Volume 2, Part 2, Revision 4

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 development 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. The manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries. This volume discusses the following functional modules: MORSE-SGC; HEATING 7.2; KENO V.a; JUNEBUG-II; HEATPLOT-S; REGPLOT 6; PLORIGEN; and OCULAR

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as TI95012012; NTIS; GPO.

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Additional details

Publishing Information

Imprint Pagination
853 p.
Report number
NUREG/CR--0200-Vol.2-Pt.2-Rev.4

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26074545
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
Descriptors DEC
COMPUTER CODES; CONTAINERS; DOCUMENT TYPES; ENERGY SOURCES; ENERGY TRANSFER; FUELS; MATERIALS; REACTOR MATERIALS

Optional Information