Results 21 to 30 of about 308 (200)
Metals, 2023 This paper presents the results of atom probe tomography studies on radiation-induced phase formation in light-water reactor pressure vessel steels after neutron irradiation under various conditions in comparison with the literature data.
Svetlana Fedotova, Evgenia Kuleshova
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Numerical investigation on stress corrosion cracking behavior of dissimilar weld joints in pressurized water reactor plants [PDF]
Fracture and Structural Integrity, 2014 There have been incidents recently where stress corrosion cracking (SCC) observed in the dissimilar metal weld (DMW) joints connecting the reactor pressure vessel (RPV) nozzle with the hot leg pipe.
Lingyan Zhao +3 more
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CHIMIA, 2005 The environmentally assisted initiation and propagation of cracks in structural materials is one of the most important degradation and ageing mechanisms in light water reactors (LWR) and may seriously affect plant availability and economics.
Hans-Peter Seifert, Stefan Ritter
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Metals, 2023 The use of mini-CT specimens for the fracture characterization of structural steels is currently a topic of great interest from both scientific and technical points of view, mainly driven by the needs and requirements of the nuclear industry.
Marcos Sánchez +5 more
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Effect of Neutron Fluence Rate on Irradiation Embrittlement of Low-copper RPV Steel
Yuanzineng kexue jishuThe reactor pressure vessels (RPVs) of pressurized water reactor (PWR) nuclear power plants currently in operation and under construction in China are all made of low-alloy ferritic steels obtained by quenching and tempering treatments (which meet the ...
WU Yazhen, LI Guoyun, WANG Haidong, HUANG Juan, ZHANG Haisheng, SUN Kai, LEI Yang, ZHU Lini
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HPC atomic simulations of defect formation and kinetic Monte Carlo simulation of material ageing [PDF]
EPJ Web of ConferencesKinetic Monte Carlo (KMC) simulations are developed to simulate microstructure evolution under irradiation of structural materials of nuclear power plants. Methods based on rigid lattice atomic KMC and object KMC, despite some approximations, present the
Domain Christophe +6 more
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AIP Advances, 2020 We report results of measurements of first-order reversal curves (FORCs) for neutron irradiated reactor pressure vessel steels to seek their possible application to a nondestructive evaluation of the irradiation hardening.
Satoru Kobayashi +5 more
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Corrosion and Materials Degradation, 2022 Low-alloy reactor pressure vessel steels have a rather low susceptibility to stress corrosion cracking (SCC) in a boiling water reactor (BWR) environment if the high-temperature water contains no anionic impurities.
Stefan Ritter, Hans-Peter Seifert
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Advanced Materials, EarlyView.A sustainable δ‐lactone‐based polymer platform enables multimodal additive manufacturing through DLP, DIW, and FFF, combining tunable crystallinity, photocurable networks, mechanical robustness, and functional response. The printed materials can be mechanically reprocessed and chemically depolymerized into recoverable monomers, demonstrating a closed ...
Farzad Gholami +2 more
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MetalsReactor pressure vessel (RPV) steels are highly susceptible to irradiation embrittlement due to prolonged exposure to high temperature, high pressure, and intense neutron irradiation.
Kaikai Tang +4 more
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