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Research Progress of Steels for Nuclear Reactor Pressure Vessels

The nuclear reactor pressure vessel is an important component of a nuclear power plant. It has been used in harsh environments such as high temperature, high pressure, neutron irradiation, thermal aging, corrosion and fatigue for a long time, which puts forward higher standards for the performance r...

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Autores principales: Zhou, Linjun, Dai, Jie, Li, Yang, Dai, Xin, Xie, Changsheng, Li, Linze, Chen, Liansheng
Formato: Online Artículo Texto
Lenguaje:English
Publicado: MDPI 2022
Materias:
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9786578/
https://www.ncbi.nlm.nih.gov/pubmed/36556568
http://dx.doi.org/10.3390/ma15248761
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author Zhou, Linjun
Dai, Jie
Li, Yang
Dai, Xin
Xie, Changsheng
Li, Linze
Chen, Liansheng
author_facet Zhou, Linjun
Dai, Jie
Li, Yang
Dai, Xin
Xie, Changsheng
Li, Linze
Chen, Liansheng
author_sort Zhou, Linjun
collection PubMed
description The nuclear reactor pressure vessel is an important component of a nuclear power plant. It has been used in harsh environments such as high temperature, high pressure, neutron irradiation, thermal aging, corrosion and fatigue for a long time, which puts forward higher standards for the performance requirements for nuclear pressure vessel steel. Based on the characteristics of large size and wall thickness of the nuclear pressure vessel, combined with its performance requirements, this work studies the problems of forging technology, mechanical properties, irradiation damage, corrosion failure, thermal aging behavior and fatigue properties, and summarizes the research progress of nuclear pressure vessel materials. The influencing factors of microstructures evolution and mechanism of mechanical properties change of nuclear pressure vessel steel are analyzed in this work. The mechanical properties before and after irradiation are compared, and the influence mechanisms of irradiation hardening and embrittlement are also summarized. Although the stainless steel will be surfacing on the inner wall of nuclear pressure vessel to prevent corrosion, long-term operation may cause aging or deterioration of stainless steel, resulting in corrosion caused by the contact between the primary circuit water environment and the nuclear pressure vessel steel. Therefore, the corrosion behavior of nuclear pressure vessels materials is also summarized in detail. Meanwhile, the evolution mechanism of the microstructure of nuclear pressure vessel materials under thermal aging conditions is analyzed, and the mechanisms affecting the mechanical properties are also described. In addition, the influence mechanisms of internal and external factors on the fatigue properties, fatigue crack initiation and fatigue crack propagation of nuclear pressure vessel steel are analyzed in detail from different perspectives. Finally, the development direction and further research contents of nuclear pressure vessel materials are prospected in order to improve the service life and ensure safe service in harsh environment.
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spelling pubmed-97865782022-12-24 Research Progress of Steels for Nuclear Reactor Pressure Vessels Zhou, Linjun Dai, Jie Li, Yang Dai, Xin Xie, Changsheng Li, Linze Chen, Liansheng Materials (Basel) Review The nuclear reactor pressure vessel is an important component of a nuclear power plant. It has been used in harsh environments such as high temperature, high pressure, neutron irradiation, thermal aging, corrosion and fatigue for a long time, which puts forward higher standards for the performance requirements for nuclear pressure vessel steel. Based on the characteristics of large size and wall thickness of the nuclear pressure vessel, combined with its performance requirements, this work studies the problems of forging technology, mechanical properties, irradiation damage, corrosion failure, thermal aging behavior and fatigue properties, and summarizes the research progress of nuclear pressure vessel materials. The influencing factors of microstructures evolution and mechanism of mechanical properties change of nuclear pressure vessel steel are analyzed in this work. The mechanical properties before and after irradiation are compared, and the influence mechanisms of irradiation hardening and embrittlement are also summarized. Although the stainless steel will be surfacing on the inner wall of nuclear pressure vessel to prevent corrosion, long-term operation may cause aging or deterioration of stainless steel, resulting in corrosion caused by the contact between the primary circuit water environment and the nuclear pressure vessel steel. Therefore, the corrosion behavior of nuclear pressure vessels materials is also summarized in detail. Meanwhile, the evolution mechanism of the microstructure of nuclear pressure vessel materials under thermal aging conditions is analyzed, and the mechanisms affecting the mechanical properties are also described. In addition, the influence mechanisms of internal and external factors on the fatigue properties, fatigue crack initiation and fatigue crack propagation of nuclear pressure vessel steel are analyzed in detail from different perspectives. Finally, the development direction and further research contents of nuclear pressure vessel materials are prospected in order to improve the service life and ensure safe service in harsh environment. MDPI 2022-12-08 /pmc/articles/PMC9786578/ /pubmed/36556568 http://dx.doi.org/10.3390/ma15248761 Text en © 2022 by the authors. https://creativecommons.org/licenses/by/4.0/Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (https://creativecommons.org/licenses/by/4.0/).
spellingShingle Review
Zhou, Linjun
Dai, Jie
Li, Yang
Dai, Xin
Xie, Changsheng
Li, Linze
Chen, Liansheng
Research Progress of Steels for Nuclear Reactor Pressure Vessels
title Research Progress of Steels for Nuclear Reactor Pressure Vessels
title_full Research Progress of Steels for Nuclear Reactor Pressure Vessels
title_fullStr Research Progress of Steels for Nuclear Reactor Pressure Vessels
title_full_unstemmed Research Progress of Steels for Nuclear Reactor Pressure Vessels
title_short Research Progress of Steels for Nuclear Reactor Pressure Vessels
title_sort research progress of steels for nuclear reactor pressure vessels
topic Review
url https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9786578/
https://www.ncbi.nlm.nih.gov/pubmed/36556568
http://dx.doi.org/10.3390/ma15248761
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