Thirty years of fuels and materials information from EBR-II
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OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering
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References (33)
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1. C.E. Stevenson, The EBR-II Fuel Cycle Story, Am. Nucl. Soc., La Grange Park, Illinois, 1987
2. J.D.B. Lambert, J.H. Bottcher, R.V. Strain, K.C. Gross, M.J. Lee, J.P. Webb, R.P. Collins, S. Ukai, S. Normura, T. Odo, S. Shikaku, Run-beyond-cladding-breach oxide testing in EBR-II, International Conference on Fast Reactors Core and Fuel Structural Behavior, Inverness, Scotland, 4–6 June 1990, p. 17
3. Tsai · J. Nucl. Mater. · 1993 · 204 · 217410.1016/0022-3115(93)90220-S ↗
4. J.D.B. Lambert, W.K. Lehto, J.I. Sackett, D.J. Hill, H.P. Planchon, R.W. Lindsay, EBR-II Test Programs, International Fast Reactor Safety Meeting III, Snowbird, Utah, 12–16 August 1990, p. 181
5. Till · Adv. Nucl. Sci. Technol. · 1988 · 20 · 12710.1007/978-1-4613-9925-4_3 ↗
6. Chang · Nucl. Technol. · 1989 · 88 · 12910.13182/NT88-129 ↗
7. Laidler · Prog. Nucl. Energy · 1997 · 31 · 13110.1016/0149-1970(96)00007-8 ↗
8. Walters · Trans. Am. Nucl. Soc. · 1978 · 28 · 140
9. Mosedale · Nature · 1969 · 224 · 130110.1038/2241301b0 ↗
10. Porter · J. Nucl. Mater. · 1988 · 159 · 11410.1016/0022-3115(88)90089-X ↗
11. D.R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, Technical Information Center, US Department of Energy, 1976, p. 41810.2172/7343826 ↗
12. Walters · Nucl. Technol. · 1979 · 46 · 13410.13182/NT79-A32386 ↗
13. Walters · J. Nucl. Mater. · 1973 · 43 · 13310.1016/0022-3115(72)90147-X ↗
14. T.R. Allen, C.L. Trybus, J.I. Cole, The effects of low dose rate irradiation and thermal aging on reactor structural alloys, J. Nucl. Mater. 270 (1999) in press10.1016/S0022-3115(99)00010-0 ↗
15. Leggett · J. Nucl. Mater. · 1993 · 204 · 2310.1016/0022-3115(93)90195-5 ↗
16. K.J. Longua, D.L. Porter, R.G. Pahl, J.A. Buzzell, G.D. Hudman, Materials Examinations of the Components of EBR-II Superheater SU-712, ANL-83-103, Argonne National Laboratory, March 1984
17. Kittel · J. Nucl. Mater. · 1993 · 204 · 110.1016/0022-3115(93)90193-3 ↗
18. J.D.B. Lambert, R. Mikailim, K.C. Gross, S.M. Frank, D.C. Cutforth, P.L. Angelo, Failed fuel identification techniques for liquid metal cooled fast reactors, in: Proceedings of the International Conference Organized by the British Nuclear Energy Society, Edinburgh, 20–22 March 1995, p. 34210.2172/71382 ↗
19. Franklin · Trans. Am. Nucl. Soc. · 1971 · 14 · 632
20. C.M. Walter, G.H. Golden, N.J. Olsen, A potential fuel for LMFBRs, Argonne National Laboratory Report, ANL-7-28, 1975
21. Tracy · Trans. Am. Nucl. Soc. · 1989 · 60 · 314
22. Blake · Reactor Sci. Technol. · 1961 · 14 · 31
23. Barnes · J. Nucl. Mater. · 1964 · 11 · 13510.1016/0022-3115(64)90002-9 ↗
24. Hofman · Nucl. Technol. · 1980 · 47 · 710.13182/NT80-A32408 ↗
25. W.N. Beck, R.J. Fousek, J.H. Kittel, The irradiation behavior of high burning uranium, plutonium alloy prototype fuel element, Argonne National Laboratory, Report ANL-7388, 196810.2172/4793507 ↗
26. Walter · Nucl. Metall. · 1973 · 19 · 181
27. B.R. Seidel and R.E. Einziger, In-reactor Cladding Breach of EBR-II Driver Fuel Elements, Radiation Effects in Breeder Reactor Structural Materials, American Institute of Metallurgical Engineering, Chicago, Illinois, 1977
28. B.R. Seidel, D.L. Porter, L.C. Walters, G.L. Hofman, Experience with EBR-II driver fuel, in: Proceedings of the International Conference Reliable Fuels or Liquid Metal Reactors, Tucson, Arizona, 7–11 September 1986, pp. 2–106
29. B.R. Seidel, G.L. Batte, C.E. Lahm. R.M. Fryer, J.F. Koenig, G.L. Hofman, Off-normal performance of EBR-II driver fuel, in: Proceedings of International Conference Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona, 7–11 Sept 1986, pp. 6–48
30. Pahl · Metall. Trans. · 1990 · 21A · 186310.1007/BF02647233 ↗
31. R.G. Pahl, R.S. Wisner, M.C. Billone, G.L. Hofman, Steady state of irradiation testing of U–Pu–Zr fuel to >18 at.% burnup, in: Proceedings of the International Conference Fast Reactor Safety IV, vol. 129, Snowbird, Utah, 12–16 August 1990
32. Hofman · Metall. Trans. · 1990 · 21A · 51710.1007/BF02671924 ↗
33. Porter · Fuel Metall. Trans. · 1990 · 21A · 187110.1007/BF02647234 ↗