Prediction of Maximum Allowable Temperatures for Dry Storage of Zircaloy-Clad Spent Fuel in Inert Atmosphere
Author:
Affiliation:
1. Auburn University, Auburn, Alabama 36849
2. Battelle-Pacific Northwest Laboratories P.O. Box 999, Richland, Washington 99352
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT89-A34227
Reference19 articles.
1. Control of degradation of spent LWR (light-water reactor) fuel during dry storage in an inert atmosphere
2. Maximum allowable temperature for storage of spent nuclear reactor fuel. An interim report
3. J. WEERTMAN and J. R. WEERTMAN, Physical Metallurgy, p. 743, R. W. CAHN, Ed. North Holland Publishing Company, Amsterdam (1965).
4. Strain‐Rate Dependence of the Tensile Failure of a Polycrystalline Material at Elevated Temperatures
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1. A study on texture stability and the biaxial creep behavior of as-hydrided CWSR Zircaloy-4 cladding at the effective stresses from 55 MPa to 65 MPa and temperatures from 300 °C to 400 °C;Journal of Nuclear Materials;2022-06
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