Irradiation Behavior of Experimental Mark-II Experimental Breeder Reactor II Driver Fuel
Author:
Affiliation:
1. Argonne National Laboratory EBR-II Project 9700 South Cass Avenue, Argonne, Illinois 60439
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/NT80-A32408
Reference13 articles.
1. Statistical and Metallurgical Analyses of Experimental Mark-IA Driver Fuel Element Cladding Failures in the Experimental Breeder Reactor II
2. A theory of swelling and gas release for reactor materials
3. H. R. BRAGER, J. L. STRAALSUND, J. J. HOLMES, and J. F. BATES, “Irradiation Produced Defects in Austenitic Stainless Steel,” WHAM-FR-16, Hanford (1970).
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