Microstructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals-Reference-Cited by-同舟云学术

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Microstructure degradation of austenitic stainless steels after 45 years of operation as VVER-440 reactor internals

Published:2020-05 Issue: Volume:533 Page:152124
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Kuleshova E.A.,Fedotova S.V.,Gurovich B.A.,Frolov A.S.,Maltsev D.A.,Stepanov N.V.,Margolin B.Z.,Minkin A.J.,Sorokin A.A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference64 articles.

1. Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr-10Ni-Ti austenitic stainless steels;Gurovich;J. Nucl. Mater.,2015

2. Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30-60 years;Kalchenko;J. Nucl. Mater.,2013

3. Current understanding of radiation-induced degradation in light water reactor structural materials;Fukuya;J. Nucl. Sci. Technol.,2013

4. Physical and mechanical modeling and prediction of fracture strain and fracture toughness of irradiated austenitic steels;Margolin;Eng. Fail. Anal.,2015

5. Formulating the strength factor α for improved predictability of radiation hardening;Tan;J. Nucl. Mater.,2015

Cited by 14 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. The influence of strain-induced martensite on hardening of neutron-irradiated chromium-nickel austenitic steel;AIP Conference Proceedings;2024

2. Feasibility of Safe Operation of WWER-440-Type Nuclear Power Plants for Up to 60–70 Years;Energies;2023-05-18

3. Long-term high-temperature exposure effects on mechanical properties and structure of the 42XNM alloy after neutron irradiation in the VVER-1000. Part 2. Structural studies;Voprosy Materialovedeniya;2023-04-28

4. Influence of Surface Machining on Development of Stress Corrosion Cracking of Distribution Wheels of Main Circulation Pump in Nuclear Power Plants;Solid State Phenomena;2023-03-15

5. Radiation-induced structure of austenitic steels with different nickel content under neutron irradiation in SM-3 and BOR-60 reactors;Voprosy Materialovedeniya;2023-02-12

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