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Title: SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Control modules C4, C6

Abstract

This Manual represents Revision 5 of the user documentation for the modular code system referred to as SCALE. The history of the SCALE code system dates back to 1969 when the current Computational Physics and Engineering Division at Oak Ridge National Laboratory (ORNL) began providing the transportation package certification staff at the U. S. Atomic Energy Commission with computational support in the use of the new KENO code for performing criticality safety assessments with the statistical Monte Carlo method. From 1969 to 1976 the certification staff relied on the ORNL staff to assist them in the correct use of codes and data for criticality, shielding, and heat transfer analyses of transportation packages. However, the certification staff learned that, with only occasional use of the codes, it was difficult to become proficient in performing the calculations often needed for an independent safety review. Thus, shortly after the move of the certification staff to the U.S. Nuclear Regulatory Commission (NRC), the NRC staff proposed the development of an easy-to-use analysis system that provided the technical capabilities of the individual modules with which they were familiar. With this proposal, the concept of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system wasmore » born. This volume is part of the manual related to the control modules for the newest updated version of this computational package.« less

Publication Date:
Research Org.:
Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Material Safety and Safeguards; Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
469124
Report Number(s):
NUREG/CR-0200-Rev.5-Vol.1-Pt.1; ORNL/NUREG/CSD-2/R5
ON: TI97005353; TRN: 97:010322
DOE Contract Number:
AC05-96OR22464
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Mar 1997
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; S CODES; MANUALS; RADIOACTIVE MATERIALS; TRANSPORT REGULATIONS; SAFETY ANALYSIS; CRITICALITY; LICENSING; COMPUTER CALCULATIONS

Citation Formats

NONE. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Control modules C4, C6. United States: N. p., 1997. Web. doi:10.2172/469124.
NONE. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Control modules C4, C6. United States. doi:10.2172/469124.
NONE. Sat . "SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Control modules C4, C6". United States. doi:10.2172/469124. https://www.osti.gov/servlets/purl/469124.
@article{osti_469124,
title = {SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Control modules C4, C6},
author = {NONE},
abstractNote = {This Manual represents Revision 5 of the user documentation for the modular code system referred to as SCALE. The history of the SCALE code system dates back to 1969 when the current Computational Physics and Engineering Division at Oak Ridge National Laboratory (ORNL) began providing the transportation package certification staff at the U. S. Atomic Energy Commission with computational support in the use of the new KENO code for performing criticality safety assessments with the statistical Monte Carlo method. From 1969 to 1976 the certification staff relied on the ORNL staff to assist them in the correct use of codes and data for criticality, shielding, and heat transfer analyses of transportation packages. However, the certification staff learned that, with only occasional use of the codes, it was difficult to become proficient in performing the calculations often needed for an independent safety review. Thus, shortly after the move of the certification staff to the U.S. Nuclear Regulatory Commission (NRC), the NRC staff proposed the development of an easy-to-use analysis system that provided the technical capabilities of the individual modules with which they were familiar. With this proposal, the concept of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system was born. This volume is part of the manual related to the control modules for the newest updated version of this computational package.},
doi = {10.2172/469124},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Mar 01 00:00:00 EST 1997},
month = {Sat Mar 01 00:00:00 EST 1997}
}

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