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Title: The SCALE Criticality Safety Analysis sequences: Status and Future Directions

Conference · · Transactions of the American Nuclear Society
OSTI ID:5996354
 [1]
  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 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 the calculation of keff. The criticality analysis sequences provided in SCALE-4 are summarized in Table 1. 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 efforts to improve system portability and user interfaces and to provide information on going 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)
OSTI ID:
5996354
Report Number(s):
CONF-930601-; CODEN: TANSAO
Journal Information:
Transactions of the American Nuclear Society, Vol. 68; Conference: American Nuclear Society (ANS) Annual Meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
Publisher:
American Nuclear Society
Country of Publication:
United States
Language:
English