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Benchmarking computer codes for cask development

Conference · · Nucl. Mater. Manage. Annu. Meet. Proc.; (United States)
OSTI ID:5793714

Sandia National Laboratories has taken the lead in developing a series of standard problems to evaluate structural and thermal computer codes used in the development of nuclear materials packagings for the United States Department of Energy (DOE). These problems were designed to simulate the hypothetical accident conditions given in Title 10 of the Code of Federal Regulation, Part 71 (10CFR71) while retaining simple geometries. This problem set exercises the ability of the codes to model pertinent physical phenomena without requiring extensive use of computer resources. The development of the standard problem set has involved both national and international consensus groups. Nationally, both the problems and consensus solutions have been developed and discussed at Industry/Government Joint Thermal and Structural Code Information Exchange meetings. Internationally, the Organization for Economic Cooperation and Development (OECD), through its Nuclear Energy Agency's Committee on Reactor Physics, has hosted a series of Specialists' Meetings on Heat Transfer to develop standard thermal problems and solutions. Each of these activities is represented in the standard problem set and the consensus solutions. This paper presents a brief overview of the structural and thermal problem sets.

Research Organization:
Transportation Systems Technology and Analysis Div., Sandia National Labs., Albuquerque, NM 87185
DOE Contract Number:
AC04-76DP00789
OSTI ID:
5793714
Report Number(s):
CONF-870713-
Journal Information:
Nucl. Mater. Manage. Annu. Meet. Proc.; (United States), Journal Name: Nucl. Mater. Manage. Annu. Meet. Proc.; (United States) Vol. 16; ISSN NUMMB
Country of Publication:
United States
Language:
English