Search Results - "Klueh, Ronald L"

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  1. 1

    Hardening mechanisms of reduced activation ferritic/martensitic steels irradiated at 300 °C by Tanigawa, Hiroyasu, Klueh, Ronald L., Hashimoto, Naoyuki, Sokolov, Mikhail A.

    Published in Journal of nuclear materials (30-04-2009)
    “…It has been reported that reduced-activation ferritic/martensitic steels (RAFMs), such as F82H, ORNL9Cr–2WVTa, and JLF-1 showed a variety of changes in…”
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    Journal Article
  2. 2

    Effects of Inclusions on Fracture Toughness of Reduced-Activation Ferritic/Martensitic F82H-IEA Steels by Tanigawa, Hiroyasu, Sawahata, Atsushi, Sokolov, Mikhail A., Enomoto, Masato, Klueh, Ronald L., Kohyama, Akira

    Published in MATERIALS TRANSACTIONS (01-03-2007)
    “…Reduced activation ferritic/martensitic steels (RAFs) are recognized as the primary candidate structural materials for fusion blanket systems. F82H is the RAF…”
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    Journal Article
  3. 3

    Irradiation Effects on Precipitation in Reduced-Activation Ferritic/Martensitic Steels by Tanigawa, Hiroyasu, Sakasegawa, Hideo, Klueh, Ronald L.

    Published in MATERIALS TRANSACTIONS (01-03-2005)
    “…It was previously reported that reduced-activation ferritic/martensitic steels (RAFs), such as F82H-IEA and its heat treatment variant, ORNL9Cr-2WVTa, JLF-1…”
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    Journal Article
  4. 4

    Reduced-activation steels: Future development for improved creep strength by Klueh, R.L.

    Published in Journal of nuclear materials (31-08-2008)
    “…Reduced-activation steels for fusion applications were developed in the 1980s to replace the elevated-temperature commercial steels first considered. The new…”
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    Journal Article
  5. 5

    Microstructure control for high strength 9Cr ferritic–martensitic steels by Tan, L., Hoelzer, D.T., Busby, J.T., Sokolov, M.A., Klueh, R.L.

    Published in Journal of nuclear materials (01-03-2012)
    “…Ferritic–martensitic (F–M) steels with 9wt.%Cr are important structural materials for use in advanced nuclear reactors. Alloying composition adjustment, guided…”
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    Journal Article
  6. 6

    Effect of oxide species and thermomechanical treatments on the strength properties of mechanically alloyed Fe-17%Cr ferritic ODS materials by Kim Ick-Soo, Okuda Takanari, Chang-Yong, Kang, Jang-Hyun, Sung, Maziasz, Philip J, Klueh, Ronald L, Miyahara Kazuya

    Published in Metals and materials international (01-12-2000)
    “…The effects of several oxide species, such as Y203, Zr02 and MgO, and the thermomechanical treatment (TMT) after the mechanical alloying (MA) process on the…”
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    Journal Article
  7. 7

    Hardening mechanisms of reduced activation ferritic/martensitic steels irradiated at 300 degree C by Tanigawa, Hiroyasu, Klueh, Ronald L, Hashimoto, Naoyuki, Sokolov, Mikhail A

    Published in Journal of nuclear materials (30-04-2009)
    “…It has been reported that reduced-activation ferritic/martensitic steels (RAFMs), such as F82H, ORNL9Cr-2WVTa, and JLF-1 showed a variety of changes in…”
    Get full text
    Journal Article
  8. 8

    Embrittlernent of irradiated F82H in the absence of irradiation hardening by Klueh, Ronald L., Shiba, Kiyoyuki, Sokolov, Mikhail A.

    Published in Journal of nuclear materials (27-12-2008)
    “…Neutron irradiation of 7-12% Cr ferritic/martensitic steels below 425-450 °C produces microstructural defects and precipitation that cause an increase in yield…”
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    Journal Article
  9. 9

    Embrittlement of irradiated ferritic/martensitic steels in the absence of irradiation hardening by Klueh, R.L., Shiba, K., Sokolov, M.A.

    Published in Journal of nuclear materials (15-07-2008)
    “…Irradiation damage caused by neutron irradiation below 425–450 °C of 9–12% Cr ferritic/martensitic steels produces microstructural defects that cause an…”
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    Journal Article
  10. 10

    New Nano-Particle-Strengthened Ferritic/Martensitic Steels By Conventional Thermomechanical Treatment by Klueh, Ronald L, Hashimoto, Naoyuki, Maziasz, Philip J

    Published in Journal of nuclear materials (01-01-2007)
    “…For increased fusion power plant efficiency, steels for operation at 650 C and higher are sought. Based on the science of precipitate strengthening, a…”
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    Journal Article
  11. 11

    Mechanical properties of neutron-irradiated nickel-containing martensitic steels: II. Review and analysis of helium-effects studies by Klueh, R.L., Hashimoto, N., Sokolov, M.A., Maziasz, P.J., Shiba, K., Jitsukawa, S.

    Published in Journal of nuclear materials (15-10-2006)
    “…In part I of this helium-effects study on ferritic/martensitic steels, results were presented on tensile and Charpy impact properties of 9Cr–1MoVNb (modified…”
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    Journal Article
  12. 12

    Mechanical properties of irradiated 9Cr–2WVTa steel with and without nickel by Klueh, R.L., Sokolov, M.A.

    Published in Journal of nuclear materials (01-08-2007)
    “…Tensile and Charpy specimens of normalized-and-tempered ORNL 9Cr–2WVTa reduced-activation steel and that steel composition containing 2% Ni (9Cr–2WVTa–2Ni)…”
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    Journal Article Conference Proceeding
  13. 13

    Cladding and Duct Materials for Advanced Nuclear Recycle Reactors by Allen, Todd R., Busby, Jeremy T, Klueh, Ronald L, Maloy, S, Toloczko, M

    Published in JOM (1989) (01-01-2008)
    “…The expanded use of nuclear energy without risk of nuclear weapons proliferation and with safe nuclear waste disposal is a primary goal of the Global Nuclear…”
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    Journal Article
  14. 14

    Mechanical properties of neutron-irradiated nickel-containing martensitic steels: I. Experimental study by Klueh, R.L., Hashimoto, N., Sokolov, M.A., Shiba, K., Jitsukawa, S.

    Published in Journal of nuclear materials (15-10-2006)
    “…Tensile and Charpy specimens of 9Cr–1MoVNb (modified 9Cr–1Mo) and 12Cr–1MoVW (Sandvik HT9) steels and these steels doped with 2% Ni were irradiated at 300 and…”
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    Journal Article
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