SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. Volume 3. Miscellaneous. [ORIGEN-S and Standard Composition libraries]
Technical Report
·
OSTI ID:5305338
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. This volume describes the ORIGEN-S data library and the Standard Composition library.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5305338
- Report Number(s):
- NUREG/CR-0200-Vol.3; ORNL/NUREG/CSD-2/V3/R1; ON: DE83013747
- Country of Publication:
- United States
- Language:
- English
Similar Records
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation. Volume 3. Miscellaneous
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]
Technical Report
·
Fri Nov 30 23:00:00 EST 1984
·
OSTI ID:5800391
SCALE: a modular code system for performing standardized computer analyses for licensing evaluation
Technical Report
·
Thu Dec 31 23:00:00 EST 1981
·
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
·
OSTI ID:5721352
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420203* -- Engineering-- Handling Equipment & Procedures
CASKS
COMPUTER CODES
CONTAINERS
CRITICALITY
DATA ANALYSIS
DOCUMENT TYPES
ENERGY TRANSFER
FISSION PRODUCTS
HEAT TRANSFER
ISOTOPE RATIO
ISOTOPES
LICENSING
MANUALS
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEAR DATA COLLECTIONS
NUCLEAR FACILITIES
RADIOACTIVE MATERIALS
SHIELDING
US NRC
US ORGANIZATIONS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420203* -- Engineering-- Handling Equipment & Procedures
CASKS
COMPUTER CODES
CONTAINERS
CRITICALITY
DATA ANALYSIS
DOCUMENT TYPES
ENERGY TRANSFER
FISSION PRODUCTS
HEAT TRANSFER
ISOTOPE RATIO
ISOTOPES
LICENSING
MANUALS
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEAR DATA COLLECTIONS
NUCLEAR FACILITIES
RADIOACTIVE MATERIALS
SHIELDING
US NRC
US ORGANIZATIONS