Development of Materials for Fast Reactor Fuel Assemblies
Author:
Affiliation:
1. Westinghouse Hanford Materials Engineering, P. O. Box 1970 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/NT87-A34012
Reference11 articles.
1. “A Summary Description of the Fast Flux Test Facility,” HEDL-400, Hanford Engineering Development Laboratory (1980).
2. Voids in Irradiated Stainless Steel
3. Recent insights on the swelling and creep of irradiated austenitic alloys
4. D. R. OLANDER, “Fundamental Aspects of Nuclear Reactor Fuel Elements,” TID-26711-P1, National Technical Information Service (1983).
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