Results 21 to 30 of about 1,250 (204)

Radiation embrittlement of reactor pressure vessel materials of Rivne NPP unit 1 due to re-irradiation after recovery annealing

Ядерна фізика та енергетика, 2019
The results of surveillance-specimens testing of re-irradiated after recovery annealing reactor pressure vessel (RPV) metal of Rivne NPP unit 1 are presented. The radiation strengthening and shift of critical temperature of brittleness for RPV base metal
M. G. Holiak, G. P. Grynchenko, V. M. Revka, O. V. Trygubenko, Yu. V. Chaykovskyi, L. I. Chyrko, O. V. Shkapyak   +6 more
doaj   +1 more source

Low-temperature embrittlement and fracture of metals with different crystal lattices – Dislocation mechanisms

Nuclear Materials and Energy, 2016
The state of a low-temperature embrittlement (cold brittleness) and dislocation mechanisms for formation of the temperature of a ductile-brittle transition and brittle fracture of metals (mono- and polycrystals) with various crystal lattices (BCC, FCC ...
V.M. Chernov, B.K. Kardashev, K.A. Moroz
doaj   +1 more source

Micromagnetic Characterization of Operation-Induced Damage in Charpy Specimens of RPV Steels

Applied Sciences, 2021
The embrittlement of two types of nuclear pressure vessel steel, 15Kh2NMFA and A508 Cl.2, was studied using two different methods of magnetic nondestructive testing: micromagnetic multiparameter microstructure and stress analysis (3MA-X8) and magnetic ...
Madalina Rabung, Melanie Kopp, Antal Gasparics, Gábor Vértesy, Ildikó Szenthe, Inge Uytdenhouwen, Klaus Szielasko   +6 more
doaj   +1 more source

Analysis of Shift in Nil-Ductility Transition Reference Temperature for RPV Steels Due to Irradiation Embrittlement Using Probability Distributions and Gamma Process

Metals
Reactor 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, Yan Li, Yuebing Li, Weiya Jin, Jiameng Liu   +4 more
doaj   +1 more source

Proton irradiation-decelerated intergranular corrosion of Ni-Cr alloys in molten salt

Nature Communications, 2020
The effects of ionizing radiation on materials often reduce to “bad news”. Radiation damage usually leads to detrimental effects such as embrittlement, accelerated creep, phase instability, and radiation-altered corrosion.
Weiyue Zhou, Yang Yang, Guiqiu Zheng, Kevin B. Woller, Peter W. Stahle, Andrew M. Minor, Michael P. Short   +6 more
doaj   +1 more source

Interatomic Fe-H potential for irradiation and embrittlement simulations [PDF]

Computational Materials Science, 2016
23 pages, 4 color figures; identical in content to the published ...
Kuopanportti, Pekko, Hayward, Erin, Fu, Chu-Chun, Kuronen, Antti, Nordlund, Kai   +4 more
openaire   +2 more sources

Development and Validation of Radiation Embrittlement Prediction Model of Austenitic Stainless Steel

Yuanzineng kexue jishu
Austenitic stainless steels are used as important structural materials in nuclear reactors due to their high fracture toughness. In the process of long-term service, austenitic stainless steel will be subjected to neutron irradiation to cause ...
JIA Lixia, WANG Dongjie, HE Xinfu, WU Shi, YANG Wen
doaj   +1 more source

Entropy‐Driven Design of Low‐Melting‐Point Alloys via Compositionally Complex Strategy

Advanced Engineering Materials, EarlyView.
Conventional low‐melting‐point alloys (LMPAs) are limited by a narrow compositional space and inherent property trade‐offs. This review presents an entropy‐driven design strategy that overcomes these limitations, ushering in a new class of low‐melting‐point compositionally complex alloys (LMCCAs).
Yinghui Shang, Jianxiang Zhao, Zhaoqi Chen, Hao Gong, Yinsen Yan, Junlei Tao, Yong Yang   +6 more
wiley   +1 more source

Nuclear Reactor Pressure Vessel Welds: A Critical and Historical Review of Microstructures, Mechanical Properties, Irradiation Effects, and Future Opportunities

Materials & Design
The nuclear reactor pressure vessel (RPV) is the most critical pressure boundary and safety structure in a nuclear power plant, as it contains the reactor core and coolant.
Jasmyne N. Emerson, Elliot H. Marrero-Jackson, Grayson A. Nemets, Maria A. Okuniewski, Janelle P. Wharry   +4 more
doaj   +1 more source

Gallium Microalloying in Bi–Sn Solders: Interfacial Phase Formation, Wettability, and Long‐Term Shear Reliability Under Isothermal Aging

Advanced Engineering Materials, EarlyView.
Gallium microalloying redirects interfacial reactions in low‐temperature Bi–Sn solders from Cu–Sn toward Cu–Ga intermetallic formation. The resulting Cu–Ga layer suppresses intermetallic growth during thermal aging, alters fracture pathways, and improves interfacial stability.
Iva Králová, Markéta Klimtová, Mohd Faizul Mohd Sabri, Yew Hoong Wong, Petr Veselý, Martin Plaček, Karel Dušek   +6 more
wiley   +1 more source