Search Results - "Grossbeck, M."

Retention of hydrogen in fcc metals irradiated at temperatures leading to high densities of bubbles or voids by Garner, F.A., Simonen, E.P., Oliver, B.M., Greenwood, L.R., Grossbeck, M.L., Wolfer, W.G., Scott, P.M.

“…Large amounts of hydrogen and helium are generated in structural metals in accelerator-driven systems. It is shown that under certain conditions, hydrogen can…”
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The Influence of lithium environment on tensile behavior and microstructure of V–4Cr–4Ti by Li, Meimei, Hoelzer, D.T., Grossbeck, M.L.

“…Thermal tests exposed V–4Cr–4Ti in static liquid lithium at 700 and 800 °C for 250, 500, and 1000 h. Post-exposure examination included chemical analysis of…”
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Irradiation creep of the US Heat 832665 of V–4Cr–4Ti by Li, Meimei, Hoelzer, D.T., Grossbeck, M.L., Rowcliffe, A.F., Zinkle, S.J., Kurtz, R.J.

“…The paper presents irradiation creep data for V –4Cr –4Ti irradiated to 3.7 dpa at 425 and 600 °C in the HFIR-17J experiment. Creep deformation was…”
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Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773 K up to 5 dpa by Ando, M., Li, M., Tanigawa, H., Grossbeck, M.L., Kim, S., Sawai, T., Shiba, K., Kohno, Y., Kohyama, A.

“…The irradiation creep behavior of F82H and several variants of JLF-1 steel has been measured at 573 and 773 K up to 5 dpa using helium-pressurized creep tubes…”
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Impurity effects on reduced-activation ferritic steels developed for fusion applications by Klueh, R.L., Cheng, E.T., Grossbeck, M.L., Bloom, E.E.

“…Reduced-activation steels are being developed for fusion applications by restricting alloying elements that produce long-lived radioactive isotopes when…”
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Biaxial thermal creep of two heats of V4Cr4Ti at 700 and 800 °C in a liquid lithium environment by Li, Meimei, Nagasaka, T., Hoelzer, D.T., Grossbeck, M.L., Zinkle, S.J., Muroga, T., Fukumoto, K., Matsui, H., Narui, M.

“…This paper presents biaxial thermal creep results for the vanadium alloy V4Cr4Ti in liquid lithium using US Heat 832665 and two batches of tubing made from…”
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Effects of post-weld heat treatment conditions on hardness, microstructures and impact properties of vanadium alloys by Nagasaka, T, Muroga, T, Grossbeck, M.L, Yamamoto, T

“…Gas-tungsten-arc (GTA) weld joints were made from V–4Cr–4Ti alloys in which oxygen levels at the weld metal ranged from 73 to 355 wppm. Both the weld metal and…”
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Creep of V–4Cr–4Ti in a lithium environment by Grossbeck, M.L

“…Biaxial creep specimens of V–4Cr–4Ti were exposed to liquid lithium at 665 and 765 °C to complement similar tests in a vacuum environment. Although the Li…”
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Gas tungsten arc welding of vanadium alloys with impurity control by Grossbeck, M.L., King, J.F., Nagasaka, T., David, S.A.

“…Gas tungsten arc welding in vanadium alloys is controlled by interstitial impurities. Techniques have been developed to weld V–4Cr–4Ti in a high-purity argon…”
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Microstructure–fracture toughness relationship of vanadium alloy/stainless steel brazed joints by Gan, Y.X, Aglan, H.A, Steward, R.V, Chin, B.A, Grossbeck, M.L

“…In this work, brazing V–5Ti–5Cr to 304 stainless steel (SS 304) using Au–18Ni alloy as filler material was conducted under high vacuum condition. Sessile drop…”
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Fracture toughness and tensile behavior of ferritic–martensitic steels irradiated at low temperatures by Rowcliffe, A.F, Robertson, J.P, Klueh, R.L, Shiba, K, Alexander, D.J, Grossbeck, M.L, Jitsukawa, S

“…Disk compact tension and sheet tensile specimens of the ferritic-martensitic steels F82H and Sandvik HT-9 were irradiated in the High Flux Isotope Reactor…”
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Effects of low temperature neutron irradiation on deformation behavior of austenitic stainless steels by Pawel, J.E., Rowcliffe, A.F., Alexander, D.J., Grossbeck, M.L., Shiba, K.

“…Two experiments have been conducted to quantify the effects of neutron irradiation on the deformation and fracture behavior of solution annealed austenitic…”
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Effect of composition on the fatigue failure behavior of vanadium alloys by Aglan, H.A, Gan, Y.X, Chin, B.A, Grossbeck, M.L

“…In this work, the effect of composition on the fracture surface morphology and fatigue failure behavior of two vanadium alloys (V–4Ti–4Cr and V–5Ti–5Cr) under…”
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Development of techniques for welding V–Cr–Ti alloys by Grossbeck, M.L., King, J.F., Alexander, D.J., Rice, P.M., Goodwin, G.M.

“…Welding vanadium alloys is complicated by interstitial impurity introduction and redistribution at elevated temperatures. Gas tungsten arc (GTA) welding, which…”
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The dependence of irradiation creep in austenitic alloys on displacement rate and helium to dpa ratio by Garner, F.A., Toloczko, M.B., Grossbeck, M.L.

“…Before the parametric dependencies of irradiation creep can be confidently determined, analysis of creep data requires that the various creep and non-creep…”
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Temperature dependence of the 20% cold worked 316 stainless steel steady state irradiation creep rate by Foster, John Paul, Bunde, Kermit, Grossbeck, M.L., Gilbert, E.Robert

“…The irradiation creep data from four completed tests have been analysed to show that the steady state irradiation creep rate exhibits a moderate and complex…”
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Fatigue failure analysis of V–4Ti–4Cr alloy by Aglan, H., Gan, Y.X., Chin, B., Grossbeck, M.

“…In the present work, the fatigue fracture and failure behavior of a V–4Ti–4Cr has been studied. Static tests were conducted to study the overloading behavior…”
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The effect of an applied stress on the welding of irradiated steels by Wang, C.A., Grossbeck, M.L., Aglan, H., Chin, B.A.

“…Previous attempts to weld irradiated and helium doped steels under constrained conditions have shown that helium concentrations as low as 2 to 3 appm can lead…”
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Analysis of V–Cr–Ti alloys in terms of activation of impurities by Grossbeck, M.L, Klueh, R.L, Cheng, E.T, Peterson, J.R, Woolery, M.R, Bloom, E.E

“…Vanadium alloys offer many advantages including reduced neutron activation. However, activation of V–Cr–Ti alloys is controlled by impurities. This study…”
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Creep Deformation in V-4Cr-4Ti in a Low-Oxygen Lithium Environment by Grossbeck, ML

“…Vanadium alloys, especially V-Cr-Ti alloys, are candidates for first wall and blanket structures of fusion reactors. However, a major vulnerability of this…”
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