Search Results - Tsai, Hanchung

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  1. 1
    Full-length U–xPu–10Zr (x=0, 8, 19wt.%) fast reactor fuel test in FFTF

    Full-length U–xPu–10Zr (x=0, 8, 19wt.%) fast reactor fuel test in FFTF by Porter, D.L., Tsai, Hanchung

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  2. 2
    Examination of Spent Pressurized Water Reactor Fuel Rods After 15 Years in Dry Storage

    Examination of Spent Pressurized Water Reactor Fuel Rods After 15 Years in Dry Storage by Einziger, Robert E., Tsai, Hanchung, Billone, Michael C., Hilton, Bruce A.

    Published in Nuclear technology
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  3. 3
    Strain-rate effects on microstructural deformation in irradiated 316 SS

    Strain-rate effects on microstructural deformation in irradiated 316 SS by Cole, James I., Tsai, Hanchung, Allen, Todd R., Yoshitake, Tsunemitsu, Akasaka, Naoaki, Yamagata, Ichiro, Nakamura, Yasuo

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  4. 4
    The effect of dose rate on the response of austenitic stainless steels to neutron radiaiton

    The effect of dose rate on the response of austenitic stainless steels to neutron radiaiton by Allen, T. R., Cole, J I., Trybus, Carole L., Porter, D. L., Tsai, Hanchung, Garner, Francis A., Kenik, E A., Yoshitake, T., Ohta, Joji

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  5. 5
    Behavior of Irradiated Type 316 Stainless Steels under Low-Strain-Rate Tensile Conditions

    Behavior of Irradiated Type 316 Stainless Steels under Low-Strain-Rate Tensile Conditions by Yoshitake, T, Yamagata, I, Akasaka, N, Nakamura, Y, Tsai, H, Cole, J, Allen, T

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  6. 6
    Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II

    Low Strain-Rate Microstructural Deformation Behavior in 316 Stainless Steel Irradiated in EBR-II by Cole, JI, Allen, TR, Tsai, H, Yoshitake, T, Yamagata, I, Akasaka, N, Nakamura, Y

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  7. 7
    Neutronics aspects of a DHCE experiment

    Neutronics aspects of a DHCE experiment by Gomes, Itacil C, Tsai, Hanchung, Smith, Dale L

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