Tensile Properties and Annealing Characteristics of H. B. Robinson Spent Fuel Cladding
Author:
Affiliation:
1. Battelle Memorial Institute, 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/NT78-A32120
Reference25 articles.
1. M. KANGILASKI, “The Effects of Neutron Irradiation on Structural Materials,” REIC Report No. 45, pp. 36–62, Battelle Memorial Institute (June 30, 1967).
2. Effect of neutron irradiation on the tensile properties of zircaloy-2 and zircaloy-4
3. Burst Testing of Zircaloy Cladding from Irradiated Pickering-Type Fuel Bundles
4. F. H. MEGERTH, “Zircaloy Clad-UO2Fuel Rod Evaluation Program,” GEAP-10070, General Electric Company (July 1969).
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