SCALE: a modular code system for performing standardized computer analyses for licensing evaluation
Technical Report
·
OSTI ID:5358952
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 2 contains documentations for the following functional modules used in the SCALE system: KENO-V which is an improved Monte Carlo criticality program; and JUNEBUG, a three-dimensional geometry plotting code.
- Research Organization:
- Union Carbide Corp., Oak Ridge, TN (USA). Nuclear Div.
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5358952
- Report Number(s):
- NUREG/CR-0200-Vol.2-Bk.3; ORNL/NUREG/CSD-2-Vol.2-Bk.3; ON: DE82013369
- Country of Publication:
- United States
- Language:
- English
Similar Records
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. [Additions]
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. Volume 2. Functional modules
Technical Report
·
Thu Dec 31 23:00:00 EST 1981
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OSTI ID:5360496
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. [Additions]
Technical Report
·
Wed Jun 01 00:00:00 EDT 1983
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OSTI ID:5721352
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. Volume 2. Functional modules
Technical Report
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Wed Jun 01 00:00:00 EDT 1983
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OSTI ID:5870163
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ABSTRACTS
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
DOCUMENT TYPES
EVALUATION
LEADING ABSTRACT
LICENSING
MATERIALS
MONTE CARLO METHOD
NATIONAL ORGANIZATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR FACILITIES
PACKAGING
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
SIMULATION
US NRC
US ORGANIZATIONS
Inspection
& Accountability-- Nontechnical Aspects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ABSTRACTS
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
DOCUMENT TYPES
EVALUATION
LEADING ABSTRACT
LICENSING
MATERIALS
MONTE CARLO METHOD
NATIONAL ORGANIZATIONS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR FACILITIES
PACKAGING
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
SIMULATION
US NRC
US ORGANIZATIONS