Search Results - "ODETTE, G. R"

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  1. 1

    Recent Progress in Developing and Qualifying Nanostructured Ferritic Alloys for Advanced Fission and Fusion Applications by Odette, G. R.

    Published in JOM (1989) (01-12-2014)
    “…This article summarizes the recent progress on developing a class of potentially transformational structural materials called nanostructured ferritic alloys,…”
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    Journal Article
  2. 2

    Irradiation-tolerant nanostructured ferritic alloys: Transforming helium from a liability to an asset by Odette, G. R., Hoelzer, D. T.

    Published in JOM (1989) (01-09-2010)
    “…Nanostructuredferritic alloys (NFAs) have the potential to make transformational contributions to developing advanced sources of fission and fusion energy…”
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    Journal Article
  3. 3

    On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys by Alinger, M.J., Odette, G.R., Hoelzer, D.T.

    Published in Acta materialia (2009)
    “…An extensive experimental study characterizing the sequence of events that lead to the formation of a very high density of Y–Ti–O solute nanoclusters (NC) in…”
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  4. 4

    On the remarkable thermal stability of nanostructured ferritic alloys by Cunningham, N., Wu, Y., Klingensmith, D., Odette, G.R.

    “…We explore the high-temperature thermal stability of a class of potentially transformational materials for high temperature applications that we call…”
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  5. 5

    On the Elevated Temperature Thermal Stability of Nanoscale Mn-Ni-Si Precipitates Formed at Lower Temperature in Highly Irradiated Reactor Pressure Vessel Steels by Almirall, N., Wells, P. B., Ke, H., Edmondson, P., Morgan, D., Yamamoto, T., Odette, G. R.

    Published in Scientific reports (03-07-2019)
    “…Atom probe tomography (APT) and scanning transmission electron microscopy (STEM) techniques were used to probe the long-time thermal stability of nm-scale…”
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  6. 6

    A physically-based correlation of irradiation-induced transition temperature shifts for RPV steels by Eason, E.D., Odette, G.R., Nanstad, R.K., Yamamoto, T.

    Published in Journal of nuclear materials (01-02-2013)
    “…This paper presents a physically-based, empirically calibrated model for estimating irradiation-induced transition temperature shifts in reactor pressure…”
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  7. 7

    Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket by Tanigawa, H., Shiba, K., Möslang, A., Stoller, R.E., Lindau, R., Sokolov, M.A., Odette, G.R., Kurtz, R.J., Jitsukawa, S.

    Published in Journal of nuclear materials (01-10-2011)
    “…The status and key issues of reduced activation ferritic/martensitic (RAFM) steels R&D are reviewed as the primary candidate structural material for fusion…”
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    Journal Article Conference Proceeding
  8. 8

    Reactive gas atomization processing for Fe-based ODS alloys by Rieken, J.R., Anderson, I.E., Kramer, M.J., Odette, G.R., Stergar, E., Haney, E.

    Published in Journal of nuclear materials (01-09-2012)
    “…► Gas atomization reaction synthesis used for precursor powders of ODS ferritic steel. ► Internal O exchange reactions were used to form Y-enriched nano-metric…”
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    Journal Article Conference Proceeding
  9. 9

    Status of reduced activation ferritic/martensitic steel development by Baluc, N., Gelles, D.S., Jitsukawa, S., Kimura, A., Klueh, R.L., Odette, G.R., van der Schaaf, B., Yu, Jinnan

    Published in Journal of nuclear materials (01-08-2007)
    “…Recent research results obtained in Europe, Japan, China and the USA on reduced activation ferritic/martensitic (RAFM) steels are reviewed. The present status…”
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    Journal Article Conference Proceeding
  10. 10

    Influence of particle dispersions on the high-temperature strength of ferritic alloys by Hoelzer, D.T., Bentley, J., Sokolov, M.A., Miller, M.K., Odette, G.R., Alinger, M.J.

    Published in Journal of nuclear materials (01-08-2007)
    “…Four ferritic alloys based on the composition Fe–14Cr–3W–0.4Ti (nominal wt%) were developed with a predominant dispersion of either oxide particles or…”
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    Journal Article Conference Proceeding
  11. 11

    Atomic scale investigation of radiation-induced segregation in austenitic stainless steels by Etienne, A., Radiguet, B., Cunningham, N.J., Odette, G.R., Pareige, P.

    Published in Journal of nuclear materials (15-11-2010)
    “…Radiation-induced precipitation and segregation in a cold-worked 316 austenitic stainless steel irradiated with 10 MeV Fe 5+ ions were characterized by atom…”
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    Journal Article
  12. 12

    Evidence for core–shell nanoclusters in oxygen dispersion strengthened steels measured using X-ray absorption spectroscopy by Liu, S., Odette, G.R., Segre, C.U.

    Published in Journal of nuclear materials (01-02-2014)
    “…Nanostructured ferritic alloys (NFA) dispersion strengthened by an ultra high density of Y–Ti–O enriched nano-features (NF) exhibit superior creep strength and…”
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  13. 13

    Thermal stability of nano-structured ferritic alloy by Miao, P., Odette, G.R., Yamamoto, T., Alinger, M., Klingensmith, D.

    Published in Journal of nuclear materials (30-06-2008)
    “…The excellent tensile and creep strength and the potential for managing radiation damage make nano-structured ferritic alloys (NFAs) promising candidates for…”
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    Journal Article Conference Proceeding
  14. 14

    Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications by Kurtz, R.J., Alamo, A., Lucon, E., Huang, Q., Jitsukawa, S., Kimura, A., Klueh, R.L., Odette, G.R., Petersen, C., Sokolov, M.A., Spätig, P., Rensman, J.-W.

    Published in Journal of nuclear materials (30-04-2009)
    “…Significant progress has been achieved in the international research effort on reduced activation ferritic/martensitic steels for fusion structural…”
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    Journal Article Conference Proceeding
  15. 15

    Helium transport, fate and management in nanostructured ferritic alloys: In situ helium implanter studies by Odette, G.R., Miao, P., Edwards, D.J., Yamamoto, T., Kurtz, R.J., Tanigawa, H.

    Published in Journal of nuclear materials (01-10-2011)
    “…High helium levels produced in fusion neutron spectra may lead to severe increases in the brittle fast fracture temperature, enhanced void swelling and…”
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    Journal Article Conference Proceeding
  16. 16

    On the effect of dose rate on irradiation hardening of RPV steels by Odette, G.R., Yamamoto, T., Klingensmith, D.

    Published in Philosophical magazine (2003. Print) (01-02-2005)
    “…The effect of dose rate (DR), or neutron flux (ϕ), on irradiation hardening (Δσ y ) and embrittlement of reactor pressure vessel (RPV) steels is a key…”
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    Journal Article Conference Proceeding
  17. 17

    The transport and fate of helium in nanostructured ferritic alloys at fusion relevant He/dpa ratios and dpa rates by Yamamoto, T., Odette, G.R., Miao, P., Hoelzer, D.T., Bentley, J., Hashimoto, N., Tanigawa, H., Kurtz, R.J.

    Published in Journal of nuclear materials (01-08-2007)
    “…A novel in situ 59Ni(n,α) reaction He-implanter technique is described, that can be used to characterize the effect of the He/dpa ratio on microstructural…”
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    Journal Article Conference Proceeding
  18. 18

    Effect of bulk oxygen on 14YWT nanostructured ferritic alloys by Cunningham, N.J., Wu, Y., Etienne, A., Haney, E.M., Odette, G.R., Stergar, E., Hoelzer, D.T., Kim, Y.D., Wirth, B.D., Maloy, S.A.

    Published in Journal of nuclear materials (01-01-2014)
    “…The effects of oxygen variations on 14(Cr)YWT(Ti) nanostructured ferritic alloys (NFA) containing high densities of Y–Ti–O nano-features (NFs) were…”
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    Journal Article
  19. 19

    Magnetic evaluation of irradiation hardening in A533B reactor pressure vessel steels: Magnetic hysteresis measurements and the model analysis by Kobayashi, S., Yamamoto, T., Klingensmith, D., Odette, G.R., Kikuchi, H., Kamada, Y.

    Published in Journal of nuclear materials (01-03-2012)
    “…We report results of measurements of magnetic minor hysteresis loops for neutron-irradiated A533B nuclear reactor pressure vessel steels varying alloy…”
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  20. 20

    Precipitation in neutron-irradiated Fe–Cu and Fe–Cu–Mn model alloys: a comparison of APT and SANS data by Miller, M.K., Wirth, B.D., Odette, G.R.

    “…The size, number density and compositions of ultrafine copper–manganese precipitates that form in Fe–0.80at.% Cu and Fe–0.78at.% Cu–1.05at.% Mn model alloys…”
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    Journal Article Conference Proceeding