The SCALE Criticality Safety Analysis Sequences: Status and Future Directions

Conference · Sun Jun 20 00:00:00 EDT 1993

OSTI ID:6893204

Parks, C. V. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The Standardized Computer Analyses for Licensing Evaluation (SCALE) code system. Was originally conceived and developed in the late 1970s for the US Nuclear Regulatory Commission. The goal was to provide easy-to-use, yet accurate, analysis capabilities for use in evaluating the criticality safety, shielding, and heat transfer aspects of transportation packages for radioactive material. The Criticality Safety Analysis Sequences (CSAS) for SCALE were developed to automate'' problem-dependent cross-section and material processing prior to execution of the well-established XSDRNPM or KENO codes for calculation of k_eff. The criticality analysis sequences provided in SCALE-4 are summarized. The SCALE system continues to be maintained and enhanced by staff of the Computing Applications Division at Oak Ridge National Laboratory (ORNL). The purpose of this paper is to discuss recent work to improve system portability and user interfaces and to provide information on ongoing work to enhance the analysis capabilities.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6893204
• Report Number(s): CONF-930601-12; ON: DE93009717
• Resource Relation: Conference: American Nuclear Society (ANS) Annual Meeting, San Diego, CA (United States), 20-24 Jun 1993
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
97 MATHEMATICS AND COMPUTING
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
PACKAGING
LICENSING
S CODES
CONTAINERS
CRITICALITY
EVALUATION
HEAT TRANSFER
INTERFACES
PACKAGING RULES
REACTOR SAFETY
SHIELDING
US NRC
COMPUTER CODES
ENERGY TRANSFER
NATIONAL ORGANIZATIONS
REGULATIONS
SAFETY
US ORGANIZATIONS
Nuclear Criticality Safety Program (NCSP)
Standardized Computer Analyses for Licensing Evaluation (SCALE)
Code System
KENO
Criticality Safety Analysis Sequences (CSAS)
XSDRNPM
420204* - Engineering- Shipping Containers
990200 - Mathematics & Computers
050900 - Nuclear Fuels- Transport
Handling
& Storage