SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. Volume 1. Control modules

Technical Report · Sat Dec 01 04:00:00 EST 1984

OSTI ID:5681758

This manual provides documentation for a new, multi-faceted computational system called SCALE (Standardized Computer Analyses for Licensing Evaluation) that has been developed to provide a standard analysis tool for use by the NRC staff and licensees in evaluating nuclear fuel facility and package designs. The SCALE system consists of several automated analytical sequences (control modules) which perform criticality, shielding, and/or heat transfer calculations with a minimum of user-required input. The computer codes (functional modules) used within each analytical sequence can also be run in a stand-alone fashion or coupled together in a sequence determined by the user. Volume 1 describes the following control modules: a one-dimensional criticality safety analysis module; an enhanced criticality safety analysis module with an optimum pitch search option; a coupled one-dimensional depletion and shielding analysis module; an automated Monte Carlo shielding analysis module; and a two-dimensional heat transfer analysis of fuel casks. Separate abstracts are provided for each control module description.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5681758
• Report Number(s): NUREG/CR-0200-Vol.1; ORNL/NUREG/CSD-2/Vol.1; ON: TI85007563
• Country of Publication: United States
• Language: English

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ABSTRACTS
C CODES
CASKS
COMPUTER CODES
CONTAINERS
CRITICALITY
DOCUMENT TYPES
ENERGY SOURCES
ENERGY TRANSFER
FUELS
HEAT TRANSFER
KINETICS
LEADING ABSTRACT
LICENSING
MANUALS
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR FUELS
ORNL
PACKAGING
REACTOR KINETICS
REACTOR MATERIALS
S CODES
SAFETY
SHIELDING
SPENT FUEL CASKS
THERMAL ANALYSIS
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS