Actions for A comparison of spent fuel shipping cask response to 10 CFR 71 normal conditions and realistic hot day extremes [electronic resource].
A comparison of spent fuel shipping cask response to 10 CFR 71 normal conditions and realistic hot day extremes [electronic resource].
- Published
- Washington, D.C. : United States. Dept. of Energy, 1994.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- 8 pages : digital, PDF file
- Additional Creators
- Sandia National Laboratories, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- The structural properties of spent nuclear fuel shipping containers vary as a function of the cask wall temperature. An analysis is performed to determine the effect of a realistic, though bounding, hot day environment on the thermal behavior of spent fuel shipping casks. These results are compared to those which develop under a steady-state application of the prescribed normal thermal conditions of 10CFR71. The completed analysis revealed that the majority of wall temperatures, for a wide variety of spent fuel shipping cask configurations, fall well below those predicted by using the steady-state application of the regulatory boundary conditions. It was found that maximum temperatures at the cask surface occasionally lie above temperatures predicted under the regulatory condition. This is due to the conservative assumptions present in the ambient conditions used. The analysis demonstrates that diurnal temperature variations which penetrate the cask wall have maxima substantially less than the corresponding temperatures obtained when applying the steady-state regulatory boundary conditions. Therefore, it is certain that vital cask components and the spent fuel itself will not exceed the temperatures calculated by use of the steady-state interpretation of the 10CFR71 normal conditions.
- Report Numbers
- E 1.99:sand--94-0145c
E 1.99: conf-940553--10
conf-940553--10
sand--94-0145c - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
02/01/1994.
"sand--94-0145c"
" conf-940553--10"
"DE94006604"
"GB0103012"
International high-level radioactive waste management conference,Las Vegas, NV (United States),22-26 May 1994.
Manson, S.J.; Gianoulakis, S.E. - Funding Information
- AC04-94AL85000
View MARC record | catkey: 14112545