Small-angle neutron scattering study on the effect of hydrogen in irradiated reactor pressure vessel steels
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference36 articles.
1. Hydrogen Degradation of Ferrous Alloys;Bernstein,1985
2. C.R. Brinkmann, J.M. Beeston, The Effect of Hydrogen on the Ductile Properties of Irradiated Pressure Vessels, IN-1359, Rep., Idaho, Nuclear Cooperation, National Reactor Testing Station, 1972
3. Combined effects of neutron irradiation and hydrogen absorption on mechanical properties of pure iron
4. Hydrogen embrittlement of unirradiated steels for nuclear reactor pressure vessels
5. Combined effects of neutron irradiation and hydrogen absorption on tensile properties and fracture mode of steels for nuclear pressure vessel
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1. Hydrogen and Temper Embrittlement Effects on Fatigue Fracture Behaviour of 2.25Cr-1.0Mo Nuclear Reactor Pressure Vessel Steel;Lecture Notes in Mechanical Engineering;2024
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3. Microstructural characterization of the synergic effects of dynamic strain ageing and hydrogen on fracture behaviour of low-alloy RPV steels in high-temperature water environments;Materials Characterization;2020-07
4. Environmental degradation of fracture resistance in high-temperature water environments of low-alloy reactor pressure vessel steels with high sulphur or phosphorus contents;Corrosion Science;2019-07
5. Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments;Corrosion Science;2019-05
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