Zobrazeno 1 - 10
of 27
pro vyhledávání: '"B.F. Kammenzind"'
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 416-432 (2019)
Zircaloy-2 and Zircaloy-4 were neutron irradiated at 358 °C in the high flux isotope reactor (HFIR) to a neutron fluence of 29.6 × 1024 n/m2 (E > 1 MeV) and the resultant irradiation hardening was measured by tensile testing. Irradiation at the rel
Externí odkaz:
https://doaj.org/article/9913587a49f9498e8fb85768812f7ea3
The role of stress-state on the low cycle fatigue resistance of non-hydrided beta-treated Zircaloy-4
Autor:
B.V. Cockeram, B.F. Kammenzind
Publikováno v:
Journal of Nuclear Materials. 576:154258
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss, Pp 416-432 (2019)
Zircaloy-2 and Zircaloy-4 were neutron irradiated at 358 °C in the high flux isotope reactor (HFIR) to a neutron fluence of 29.6 × 1024 n/m2 (E > 1 MeV) and the resultant irradiation hardening was measured by tensile testing. Irradiation at the rel
Autor:
B.F. Kammenzind, B.V. Cockeram
Publikováno v:
Journal of Nuclear Materials. 499:111-125
Cyclic stresses produced during the operation of nuclear reactors can result in the extension of cracks by processes of fatigue. Although fatigue crack growth rate (FCGR) data for Zircaloy-4 in air are available, little testing has been performed in
Akademický článek
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Publikováno v:
Journal of Nuclear Materials. 303:210-225
The high-temperature-water corrosion performance of hafnium is evaluated. Corrosion kinetic data are used to develop correlations that are a function of time and temperature. The evaluation is based on corrosion tests conducted in out-of-pile autocla
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Publikováno v:
Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors
This paper presents the effects of neutron irradiation on the fracture behavior and deformation microstructure of high-strength nickel-base alloy fastener materials, Alloy X-750 and Alloy 625. Alloy X-750 in the HTH condition, and Alloy 625 in the di
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c8e1907bef1581f0f4a9385f8ee3dec7
https://doi.org/10.1002/9781118787618.ch112
https://doi.org/10.1002/9781118787618.ch112
Zircaloy-4, which is widely used as a core structural material in Pressurized-Water Reactors (PWR), picks up hydrogen during service. Hydrogen solubility in Zircaloy-4 is low and hydrides precipitate after the Zircaloy-4 matrix becomes supersaturated
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7bc5fd6c2e89cbb8f605f355694867ba
https://doi.org/10.2172/244661
https://doi.org/10.2172/244661