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Title: SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4

Abstract

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.

Authors:
;  [1];  [1]
  1. Oak Ridge National Lab., TN (United States)
Publication Date:
Research Org.:
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 Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
72990
Report Number(s):
NUREG/CR-0200-Vol.3-Rev.4; ORNL/NUREG/CSD-2/R4-Vol.3
ON: TI95012139; TRN: 95:016267
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Apr 1995
Country of Publication:
United States
Language:
English
Subject:
99 MATHEMATICS, 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

Citation Formats

Petrie, L M, Jordon, W C, Edwards, A L, and Lawrence Livermore National Lab., CA. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4. United States: N. p., 1995. Web. doi:10.2172/72990.
Petrie, L M, Jordon, W C, Edwards, A L, & Lawrence Livermore National Lab., CA. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4. United States. https://doi.org/10.2172/72990
Petrie, L M, Jordon, W C, Edwards, A L, and Lawrence Livermore National Lab., CA. 1995. "SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4". United States. https://doi.org/10.2172/72990. https://www.osti.gov/servlets/purl/72990.
@article{osti_72990,
title = {SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4},
author = {Petrie, L M and Jordon, W C and Edwards, A L and Lawrence Livermore National Lab., CA},
abstractNote = {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.},
doi = {10.2172/72990},
url = {https://www.osti.gov/biblio/72990}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Apr 01 00:00:00 EST 1995},
month = {Sat Apr 01 00:00:00 EST 1995}
}