Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing-Reference-Cited by-同舟云学术

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Recovery of the Transition Temperature of Irradiated WWER-440 Vessel Metal by Annealing

Published: Issue: Volume: Page:369-369-11
ISSN:
Container-title:Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review (Fourth Volume)
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Author:

Amayev AD,Kryukov AM,Sokolov MA

Publisher

ASTM International

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Recovery of neutron-irradiated VVER-440 RPV base metal and weld exposed to isothermal annealing at 343°C up to 2,000 h;Frontiers in Nuclear Engineering;2024-08-16

2. Applying the Hollomon-Jaffe parameter to predict changes in mechanical properties of irradiated austenitic chromium-nickel steels during isothermal exposure;AIMS Materials Science;2024

3. Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor;Journal of Nuclear Materials;2023-10

4. Study of the metal of the irradiated weld of the WWER-440 reactor body after 45 years of operation;Voprosy Materialovedeniya;2022-02-01

5. Multicriteria materials selection for extreme operating conditions based on a multiobjective analysis of irradiation embrittlement and hot cracking prediction models;International Journal of Mechanics and Materials in Design;2017-11-11

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