Results 1 to 10 of about 1,100 (164)
Fundamental Mechanisms for Irradiation-Hardening and Embrittlement: A Review
Metals, 2019 It has long been recognized that exposure to irradiation environments could dramatically degrade the mechanical properties of nuclear structural materials, i.e., irradiation-hardening and embrittlement.
Xiazi Xiao
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The development of prediction model on irradiation embitterment for low Cu RPV steels [PDF]
Heliyon, 2023 The development of prediction model on irradiation embitterment (PMIE) of reactor pressure vessel (RPV) is an important method for nuclear reactor long term operation.
Chaoliang Xu +7 more
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Nuclear Engineering and Technology, 2021 The prediction of irradiation-induced transition temperature shift for RPV steels is an important method for long term operation of nuclear power plant.
Chaoliang Xu +8 more
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International Journal of Advanced Nuclear Reactor Design and Technology, 2023 Reactor pressure vessel (RPV) is the most important core equipment in PWR. Its service life determines the service life of nuclear power plant and directly affects the economy and safety of nuclear power plant. Because RPV is serviced at high temperature,
Bai Bing +5 more
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Hydrogen embrittlement in irradiated steels [PDF]
Nuclear Engineering and Design, 1966 Abstract Hydrogen charging conditions that completely embrittle an ultra-high strength steel have a negligible effect on 212-B pressure vessel steel in tensile and delayed failure tests, Much higher hydrogen charges reduce the notch tensile strength.
A.D. Rossin, T.H. Blewitt, A.R. Troiano
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Metals, 2022 The neutron irradiation of Fe-based fusion and fission reactor materials leads to an increase in ductile-to-brittle transition temperature with a decrease in upper shelf energy. It is well known that Cu content has a strong influence on the embrittlement
Hideo Watanabe +3 more
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Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors
Metals, 2022 Rate theory models have been developed for the swelling and He-embrittlement of austenitic stainless steels and Ni-alloys in nuclear reactors. The models illustrate how microstructure evolution during irradiation affects the rate of change of mechanical ...
Malcolm Griffiths +2 more
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Control of Irradiation Embrittlement in Molybdenum [PDF]
Nature, 1961 IRON, steel, and other body-centred cubic metals show an increase in ductile-brittle transition temperature as a result of neutron irradiation. In an attempt to elucidate the mechanism of this embrittlement for EN2 steel, Hull and Mogford1 studied the effect of neutron irradiation on the parameters σi and k y in the Petch relation:
D. N. SETHNA +3 more
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Nuclear Engineering and Technology, 2023 This paper presents the results of investigating the change in welding residual stresses of the core shroud, which is one of subcomponents in reactor vessel internals, performing finite element analysis.
Jong-Sung Kim, Young-Chan Kim, Wan Yoo
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Mathematics, 2022 The aim of this work is to present a new analytical model to evaluate jointly the mechanical integrity and the fitness-for-service of nuclear reactor pressure-vessels steels.
Alvaro Rodríguez-Prieto +4 more
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