Search Results - "Bruemmer, S.M"

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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Study of grain boundary character along intergranular stress corrosion crack paths in austenitic alloys by Gertsman, V.Y., Bruemmer, S.M.

“…Samples of austenitic stainless alloys were examined by means of scanning and transmission electron microscopy. Misorientations were measured by electron…”
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Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 °C by Edwards, D.J, Simonen, E.P, Bruemmer, S.M

“…Six austenitic stainless steel heats (three heats each of 304SS and 316SS) neutron-irradiated at 275 °C from 0.6 to 13.3 dpa have been carefully characterized…”
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Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals by Bruemmer, S.M, Simonen, E.P, Scott, P.M, Andresen, P.L, Was, G.S, Nelson, J.L

“…Current understanding of radiation-induced material changes that occur in light-water-reactor (LWR) core components is critically reviewed and linked to…”
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Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS by Edwards, D.J, Simonen, E.P, Garner, F.A, Greenwood, L.R, Oliver, B.M, Bruemmer, S.M

“…A cold worked 316SS baffle bolt was extracted from the Tihange pressurized water reactor and sectioned at three different positions. The temperature and dose…”
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Determination of neutron exposure of AISI 304 stainless steel from a BWR top guide using retrospective dosimetry by Greenwood, L.R., Garner, F.A., Oliver, B.M., Bruemmer, S.M.

“…Retrospective dosimetry was used to determine the accumulated neutron exposure of AISI 304 stainless steel removed from the top guide of a boiling water…”
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The influence of oversized solute additions on radiation-induced changes and post-irradiation intergranular stress corrosion cracking behavior in high-purity 316 stainless steels by Fournier, L, Sencer, B.H, Was, G.S, Simonen, E.P, Bruemmer, S.M

“…The influence of oversized solute additions on the radiation-induced microstructure, radiation-induced segregation (RIS) at grain boundaries and…”
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Decoupling the role of stress and corrosion in the intergranular cracking of noble-metal alloys by Badwe, N., Chen, X., Schreiber, D. K., Olszta, M. J., Overman, N. R., Karasz, E. K., Tse, A. Y., Bruemmer, S. M., Sieradzki, K.

“…Intergranular stress-corrosion cracking (IGSCC) is a form of environmentally induced crack propagation causing premature failure of elemental metals and…”
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Grain-boundary structure and segregation behavior in a nickel-base stainless alloy by Baik, Sung-Il, Olszta, M.J., Bruemmer, S.M., Seidman, David N.

“…Atom-probe tomography (APT) is utilized to obtain three-dimensional chemical information concerning grain boundary (GB) segregation in a Ni–Cr–Fe alloy 600…”
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Evidence for excess vacancies at sliding grain boundaries during superplastic deformation by Vetrano, J.S, Simonen, E.P, Bruemmer, S.M

“…Rapid quenching of Al–Mg alloys during superplastic deformation has revealed the presence of nano-scale cavities along many grain boundaries. They were…”
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Lattice defect/grain boundary interactions related to IASCC by Simonen, E.P., Bruemmer, S.M.

“…Radiation-induced segregation (RIS) of major alloying elements to grain boundaries in austenitic stainless steels has emerged as a critical aspect of…”
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Grain boundary depletion and migration during selective oxidation of Cr in a Ni–5Cr binary alloy exposed to high-temperature hydrogenated water by Schreiber, D.K., Olszta, M.J., Bruemmer, S.M.

“…[Display omitted] High-resolution microscopy of a high-purity Ni–5Cr alloy exposed to 360°C hydrogenated water reveals intergranular selective oxidation of Cr…”
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Directly correlated transmission electron microscopy and atom probe tomography of grain boundary oxidation in a Ni–Al binary alloy exposed to high-temperature water by Schreiber, D.K., Olszta, M.J., Bruemmer, S.M.

“…Intergranular oxidation of a Ni–4Al alloy exposed to hydrogenated, high-temperature water was characterized using directly correlated transmission electron…”
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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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Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa by Edwards, D.J., Garner, F.A., Bruemmer, S.M., Efsing, Pål

“…The radiation-induced microstructure of a cold-worked 316SS flux thimble tube from an operating pressurized water reactor (PWR) was examined. Two irradiated…”
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Emulation of neutron irradiation effects with protons: validation of principle by Was, G.S, Busby, J.T, Allen, T, Kenik, E.A, Jensson, A, Bruemmer, S.M, Gan, J, Edwards, A.D, Scott, P.M, Andreson, P.L

“…This paper presents the results of the irradiation, characterization and irradiation assisted stress corrosion cracking (IASCC) behavior of proton- and…”
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Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70dpa by Edwards, D.J., Garner, F.A., Bruemmer, S.M., Efsing, Pål

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Composition-Based Correlations to Predict Sensitization Resistance of Austenitic Stainless Steels by Bruemmer, S. M.

“…[Repeated from Corr. Abstracts, Vol. 25, N…”
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Continuous Cooling Sensitization of Type 316 Austenitic Stainless Steel by Simmons, J.W., Atteridge, D.G., Bruemmer, S.M.

“…ABSTRACTAustenitic stainless steels become sensitized when subjected to an isothermal heat treatment within orcontinuous cooling through the temperature range…”
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High-Resolution Characterization of Intergranular Attack and Stress Corrosion Cracking of Alloy 600 in High-Temperature Primary Water by Thomas, L.E., Bruemmer, S.M.

“…ABSTRACTIntergranular (IG) attack regions and stress corrosion cracks in Alloy 600 (UNS N06600) U-bend samples tested in 330°C pressurized water reactor water…”
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