Radiation damage and transmutation in tungsten-alloys for nuclear fusion applications 著者: Lloyd, MJ

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Prismatic, basal, and slip strengths of commercially pure Zr by micro-cantilever tests 著者: Wilkinson, A

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A regression approach for Zircaloy-2 in-reactor creep constitutive equations 著者: Liu, Yung-Yuan, Bement, Arden Lee

主題: “…Nuclear reactors Materials Creep…”
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TEM characterisation of heavy-ion irradiation damage in Fe-Cr alloys 著者: Xu, S

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Micromechanical testing of irradiated tungsten for fusion 著者: Jim, B

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Modeling of corium/concrete interaction 著者: Lee, Min, Kazimi, Mujid S.

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Determination of 3-D boron distribution 著者: Fadaai, Abolghaasem.

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Effect of reactor irradiation on Santowax OM and WR 著者: Mason, Edward A. (Edward Archibald), 1924-, Lee, Min-Li, Brewer, Shelby Templeton, Bley, W. N. (William Norman)

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Friction factor and heat transfer correlation for irradiated organic coolants 著者: Swan, Arthur Henry, Mason, Edward A. (Edward Archibald), 1924-, Bley, W. N. (William Norman), Kim, Je Chul, Morgan, Dean T.

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Irradiation loop studies of organic reactor coolants 著者: Mason, Edward A. (Edward Archibald), 1924-, Bley W. N. (William Norman)

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Irradiation loop studies of organic reactor coolants : Progress report 著者: Mason, Edward A. (Edward Archibald), 1924-

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The irradiation of Santowax OMP in the M.I.T. in-pile loop 著者: Morgan, Dean T., Mason, Edward A. (Edward Archibald), 1924-

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Corrosion fatigue in nickel base alloys for nuclear steam generator applications 著者: Ballinger, Ronald George, 1945-

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On the Limitations of Positron Annihilation Spectroscopy in the Investigation of Ion-Implanted FeCr Samples 著者: Vladimir Slugen, Jarmila Degmova, Stanislav Sojak, Martin Petriska, Pavol Noga, Vladimir Krsjak

主題: “…nuclear reactor materials…”
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Co-segregation of Y and Zr in W-Cr-Y-Zr alloys: First-principles modeling at finite temperature and application to SMART materials 著者: Damian Sobieraj, Jan S. Wróbel, Mark R. Gilbert, Krzysztof J. Kurzydłowski, Duc Nguyen-Manh

主題: “…Nuclear reactor materials…”
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Presentation of the results for deuterium retention and thermal release in a new type of low activation ferritic-martensitic steel EUROFER / Результаты исследования по удержанию де... 著者: Sanja Lj. Korica

主題: “…nuclear reactor materials…”
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