The Development of an International Standard Problem Set for Thermal Code Evaluation

Conference · Sat Feb 27 23:00:00 EST 1988

OSTI ID:6469497

Glass, Robert E. ^[1]

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1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

During a preparatory meeting in Paris on June 21-22, 1979, interest was expressed by most Nuclear Energy Agency (NEA) member countries in exchanging information and experience on various aspects of spent fuel transportation. The result of this meeting was the establishment of working groups under the auspices of the Committee on Reactor Physics (CRP) in the areas of heat transfer, criticality, and shielding. The heat transfer group was established to define a set of cask-like thermal problems and to provide solutions. The problems set and its solutions are available to benchmark computer codes.

• Research Organization: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6469497
• Report Number(s): SAND-88-0506C; CONF-880201--46; ON: DE91001263
• Country of Publication: United States
• Language: English

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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
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SPENT FUEL CASKS
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