SCALE: a modular code system for performing standardized computer analyses for licensing evaluation
Technical Report
·
OSTI ID:5360496
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 alo be run in a stand-alone fashion or coupled together in a sequence determined by the user.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5360496
- Report Number(s):
- NUREG/CR-0200-Vol.2-Bk.2; ORNL/NUREG/CSD-2-Vol.2-Bk.2; ON: DE82013370
- Country of Publication:
- United States
- Language:
- English
Similar Records
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
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. [Additions]
Technical Report
·
Wed Jun 01 00:00:00 EDT 1983
·
OSTI ID:5721352
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. Volume 2. Functional modules
Technical Report
·
Wed Jun 01 00:00:00 EDT 1983
·
OSTI ID:5870163
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. [Additions]
Technical Report
·
Wed Jun 01 00:00:00 EDT 1983
·
OSTI ID:5625264
Related Subjects
055002* -- Nuclear Fuels-- Safeguards
Inspection
& Accountability-- Nontechnical Aspects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ABSTRACTS
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
DESIGN
DOCUMENT TYPES
ENERGY TRANSFER
EVALUATION
HEAT TRANSFER
LEADING ABSTRACT
LICENSING
MATERIALS
MONTE CARLO METHOD
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
PACKAGING
PHYSICS
RADIOACTIVE MATERIALS
REACTOR PHYSICS
SHIELDING
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
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ABSTRACTS
COMPUTER CODES
COMPUTERIZED SIMULATION
CRITICALITY
DESIGN
DOCUMENT TYPES
ENERGY TRANSFER
EVALUATION
HEAT TRANSFER
LEADING ABSTRACT
LICENSING
MATERIALS
MONTE CARLO METHOD
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
PACKAGING
PHYSICS
RADIOACTIVE MATERIALS
REACTOR PHYSICS
SHIELDING
SIMULATION
US NRC
US ORGANIZATIONS