New Enhancements to SCALE for Criticality Safety Analysis

Conference · Sun Sep 17 00:00:00 EDT 1995

OSTI ID:102260

Hollenbach, D. F. ^[1]; Bowman, S. M. ^[1]; Petrie, L. M. ^[1]; Parks, C. V. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division

As the speed, available memory, and reliability of computer hardware increases and the cost decreases, the complexity and usability of computer software will increase, taking advantage of the new hardware capabilities. Computer programs today must be more flexible and user friendly than those of the past. Within available resources, the SCALE staff at Oak Ridge National Laboratory (ORNL) is committed to upgrading its computer codes to keep pace with the current level of technology. This paper examines recent additions and enhancements to the criticality safety analysis sections of the SCALE code package. These recent additions and enhancements made to SCALE can be divided into nine categories: (1) new analytical computer codes, (2) new cross-section libraries, (3) new criticality search sequences, (4) enhanced graphical capabilities, (5) additional KENO enhancements, (6) enhanced resonance processing capabilities, (7) enhanced material information processing capabilities, (8) portability of the SCALE code package, and (9) other minor enhancements, modifications, and corrections to SCALE. Each of these additions and enhancements to the criticality safety analysis capabilities of the SCALE code system are discussed below.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 102260
• Report Number(s): CONF-9509100-14; ON: DE95017456; TRN: 95:020522
• Resource Relation: Conference: ICNC '95: 5. International Conference on Nuclear Criticality Safety , Albuquerque, NM (United States), 17-22 Sep 1995; Other Information: PBD: [1995]
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
SAFETY ANALYSIS
S CODES
CRITICALITY
SPENT FUEL CASKS
SPENT FUELS
NUCLEAR DATA COLLECTIONS
K CODES
MONTE CARLO METHOD
COMPUTER GRAPHICS
NUCLEAR FACILITIES
TRANSPORT
Nuclear Criticality Safety Program (NCSP)
Cross-Section Libraries
Monte Carlo Criticality Safety Computer Codes
KENO-VI
KENO-V.a
Bondarenko Shielding Factors
Pressurized-Water-Reactor (PWR)
Light-Water-Reactor (LWR)
Evaluated Nuclear Data File (ENDF)
Maxwellian Thermal Peak
Spent Fuel Shipping Cask