High Temperature Postirradiation Materials Performance of Spent Pressurized Water Reactor Fuel Rods under Dry Storage Conditions
Author:
Affiliation:
1. Hanford Engineering Development Laboratory, P.O. Box 1970 Mail Stop W/A-53, Richland, Washington 99352
2. Battelle Columbus Laboratories, 505 King Avenue, Columbus, Ohio 43201
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/NT82-A16187
Reference38 articles.
1. D. CUBICCIOTTI, “State-of-the-Art Model for Release of Volatile Fission Product from UO2Fuel,” SRI-EPRI RP 355-11, SRI International (Dec. 1978).
2. Characterization of deposits on inside surfaces of lwr cladding
3. L. D. BLACKBURN, D. G. FARWICK, S. R. FIELD, L. A. JAMES, and R. A. MOEN, “Maximum Allowable Temperature for Stroage of Spent Nuclear Reactor Fuel,” HEDL-TME-78-37, Hanford Engineering Development Laboratory (May 1978).
4. R. B. DAVIS, “Data Report for the Nondestructive Examination of Turkey Point Spent Fuel Assemblies B02, B03, B17, B41 and B43,” HEDL-TME-79-68, Hanford Engineering Development Laboratory (May 1980).
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