Search Results - "TOLOCZKO, M. B"

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure by Garner, F.A, Toloczko, M.B, Sencer, B.H

“…It is well-known that ferritic and ferritic/martensitic steels develop much less swelling than austenitic steels during neutron or charged particle…”
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Cladding and duct materials for advanced nuclear recycle reactors by Allen, T. R., Busby, J. T., Klueh, R. L., Maloy, S. A., Toloczko, M. B.

“…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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Shear punch testing of candidate reactor materials after irradiation in fast reactors and spallation environments by Maloy, S.A., Romero, T.J., Hosemann, P., Toloczko, M.B., Dai, Y.

“…Ferritic/martensitic steels and nickel-base superalloys are potential materials for use in spallation targets and fusion and fast reactors. To investigate the…”
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Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa by Toloczko, M.B., Garner, F.A., Voyevodin, V.N., Bryk, V.V., Borodin, O.V., Mel’nychenko, V.V., Kalchenko, A.S.

“…In order to study the potential swelling behavior of the ODS ferritic alloy MA957 at very high dpa levels, specimens were prepared from pressurized tubes that…”
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The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels by Maloy, Stuart A., Toloczko, M.B., McClellan, K.J., Romero, T., Kohno, Y., Garner, F.A., Kurtz, R.J., Kimura, A.

“…Tensile testing has been performed at 25 and at ∼400 °C on two ferritic/martensitic steels (JFMS and HT-9) after irradiation in FFTF to up to ∼70 dpa at…”
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High temperature tensile testing of modified 9Cr–1Mo after irradiation with high energy protons by Toloczko, M.B., Hamilton, M.L., Maloy, S.A.

“…This study examines the effect of tensile test temperatures ranging from 50 to 600 °C on the tensile properties of a modified 9Cr–1Mo ferritic steel after high…”
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Comparison of fission neutron and proton/spallation neutron irradiation effects on the tensile behavior of type 316 and 304 stainless steel by Maloy, S.A., James, M.R., Johnson, W.R., Byun, T.S., Farrell, K., Toloczko, M.B.

“…As part of the accelerator production of tritium and the spallation neutron source programs, the tensile properties of annealed 304L, 316LN and 316L stainless…”
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Linking Grain Boundary Microstructure to Stress Corrosion Cracking of Cold-Rolled Alloy 690 in Pressurized Water Reactor Primary Water by Bruemmer, S.M., Olszta, M.J., Toloczko, M.B., Thomas, L.E.

“…Grain boundary microstructures and microchemistries are examined in cold-rolled Alloy 690 (UNS N06690) materials and comparisons are made to intergranular…”
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Grain boundary selective oxidation and intergranular stress corrosion crack growth of high-purity nickel binary alloys in high-temperature hydrogenated water by Bruemmer, S.M., Olszta, M.J., Toloczko, M.B., Schreiber, D.K.

“…•IG corrosion observed for Ni-5Cr and Ni-4Al in hydrogenated water.•Grain boundary O ingress and internal oxidation for Ni-4Al, not for Ni-5Cr.•All high-purity…”
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Thermal creep mechanisms in V–4Cr–4Ti pressurized tube specimens by Gelles, D.S., Toloczko, M.B., Kurtz, R.J.

“…Pressurized thermal creep tubes of V–4Cr–4Ti have been examined following testing in the range 650–800 °C for tests lasting ∼10 4 h to provide comparison with…”
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International Round-Robin on Stress Corrosion Crack Initiation of Alloy 600 Material in Pressurized Water Reactor Primary Water by Meadows, P.J., Andresen, P.L., Toloczko, M.B., Kuang, W.-J., Ritter, S., Bjurman, M., Zhang, L., Ernestova, M., Toivonen, A., Perosanz-Lopez, F., Stairmand, J.W., Mottershead, K.J.

“…The International Cooperative Group on Environmentally Assisted Cracking of Water Reactor Materials coordinated an international “Round-Robin” collaboration of…”
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SANS and TEM of ferritic-martensitic steel T91 irradiated in FFTF up to 184 dpa at 413 °C by VAN DEN BOSCH, J, ANDEROGLU, O, DICKERSON, R, HARTL, M, DICKERSON, P, AGUIAR, J. A, HOSEMANN, P, TOLOCZKO, M. B, MALOY, S. A

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Tensile properties of the NLF reduced activation ferritic/martensitic steels after irradiation in a fast reactor spectrum to a maximum dose of 67 dpa by MALOY, Stuart A, JAMES, M. R, ROMERO, T. J, TOLOCZKO, M. B, KURTZ, R. J, KIMURA, A

“…The NLF series of steels are reduced activation ferritic-martensitic (RAFM) steels that are a part of the Japanese program to produce a suitable reduced…”
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Radiation response of alloy T91 at damage levels up to 1000 peak dpa by Gigax, J.G., Chen, T., Kim, Hyosim, Wang, J., Price, L.M., Aydogan, E., Maloy, S.A., Schreiber, D.K., Toloczko, M.B., Garner, F.A., Shao, Lin

“…Ferritic/martensitic alloys are required for advanced reactor components to survive 500–600 neutron-induced dpa. Ion-induced void swelling of…”
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Shear punch tests performed using a new low compliance test fixture by Toloczko, M.B, Kurtz, R.J, Hasegawa, A, Abe, K

“…Based on a recent finite element analysis (FEA) study performed on the shear punch test technique, it was suggested that compliance in a test frame and…”
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Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40―110 dpa at 400―750 °C in FFTF by TOLOCZKO, M. B, GARNER, F. A, MALOY, S. A

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Validation of the shear punch–tensile correlation technique using irradiated materials by Hankin, G.L, Toloczko, M.B, Hamilton, M.L, Faulkner, R.G

“…In previous studies on a variety of unirradiated materials, a linear relationship was developed between uniaxial tensile strength and effective shear strength,…”
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Analysis of possible deformation mechanisms in helium–ion irradiated SiC by Nogami, S., Ohtsuka, S., Toloczko, M.B., Hasegawa, A., Abe, K.

“…Possible modes of accommodating deformation during physically constrained swelling of SiC during He–ion irradiation (∼2×10 22 He/m 2 below 200 °C) were studied…”
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Hierarchical microstructures in CZT by Sundaram, S.K., Henager, C.H., Edwards, D.J., Schemer-Kohrn, A.L., Bliss, M., Riley, B.R., Toloczko, M.B., Lynn, K.G.

“…Advanced characterization tools, such as electron backscatter diffraction and transmitted IR microscopy, are being applied to study critical microstructural…”
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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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