SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Control modules C4, C6

Technical Report · Sat Mar 01 00:00:00 EST 1997

DOI:https://doi.org/10.2172/469124· OSTI ID:469124

This Manual represents Revision 5 of the user documentation for the modular code system referred to as SCALE. The history of the SCALE code system dates back to 1969 when the current Computational Physics and Engineering Division at Oak Ridge National Laboratory (ORNL) began providing the transportation package certification staff at the U. S. Atomic Energy Commission with computational support in the use of the new KENO code for performing criticality safety assessments with the statistical Monte Carlo method. From 1969 to 1976 the certification staff relied on the ORNL staff to assist them in the correct use of codes and data for criticality, shielding, and heat transfer analyses of transportation packages. However, the certification staff learned that, with only occasional use of the codes, it was difficult to become proficient in performing the calculations often needed for an independent safety review. Thus, shortly after the move of the certification staff to the U.S. Nuclear Regulatory Commission (NRC), the NRC staff proposed the development of an easy-to-use analysis system that provided the technical capabilities of the individual modules with which they were familiar. With this proposal, the concept of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system was born. This volume is part of the manual related to the control modules for the newest updated version of this computational package.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Material Safety and Safeguards; Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 469124
• Report Number(s): NUREG/CR--0200-Rev.5-Vol.1-Pt.1; ORNL/NUREG/CSD--2/R5; ON: TI97005353
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
42 ENGINEERING
99 GENERAL AND MISCELLANEOUS
COMPUTER CALCULATIONS
CRITICALITY
LICENSING
MANUALS
Nuclear Criticality Safety Program (NCSP)
RADIOACTIVE MATERIALS
S CODES
SAFETY ANALYSIS
TRANSPORT REGULATIONS