Irradiation behavior of U–Nb–Zr alloy dispersed in aluminum

Author:

Meyer M.K,Hofman G.L,Wiencek T.C,Hayes S.L,Snelgrove J.L

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference14 articles.

1. See for example, A. Travelli, Status and progress of the RERTR program in the year 2000, in: Proceedings of the 2000 International Meeting on Reduced Enrichment for Research and Test Reactors, Las Vegas, NV, October 1–6, 2000, Argonne National Laboratory Report ANL/TD/TM01-12, p. 3

2. Safety Evaluation Report Related to the Evaluation of Low-Enriched Uranium Silicide–Aluminum Dispersion Fuel for Use in Non-Power Reactors, NUREG-1313, United States Nuclear Regulatory Commission, 1988

3. Proceedings of the 19th International Meeting on Reduced Enrichment for Research and Test Reactors, Seoul, Korea, October 7–10, 1996;Snelgrove,1996

4. Proceedings of the 20th International Meeting on Reduced Enrichment for Research and Test Reactors, Jackson Hole, WY, October 5–10, 1997, ANL/TD/TM-99-06;Trybus,1999

5. T.C. Wiencek, Summary Report on Fuel Development and Miniplate Fabrication for the RERTR Program, 1978 to 1990, ANL/RERTR/TM-15, Argonne National Laboratory Report, 1995

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