Early-stage aqueous corrosion-related defects in heavy ion irradiated P92 ferritic/martensitic alloy

Li, Lei; Jin, Shuoxue; Yue, Shuaipeng; Chen, Yu; Diao, Qianshun; Shen, Tielong; Qiao, Yanxin

doi:10.1016/j.nimb.2023.01.010

Nuclear Instruments and Methods in Physics Research Section B:

2023

DOI: 10.1016/j.nimb.2023.01.010

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Early-stage aqueous corrosion-related defects in heavy ion irradiated P92 ferritic/martensitic alloy

Lei Li

Shuoxue Jin

Shuaipeng Yue

et al.

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2024

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Status and issues of high-temperature and high-pressure water corrosion research of fusion structural materials in Japanese DEMO reactor development

Nakajima,

Nozawa

2024

Nucl. Fusion

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The activated corrosion product (ACP) assessments of fusion structural materials are essential to designing components and evaluating workers’ radiation exposure. This paper first gives the R&D status of the high-temperature pressurized water corrosion study of reduced activation ferritic/martensitic (RAFM) steels and chromium-zirconium-copper (CuCrZr) alloys, which are the leading candidate materials of fusion reactor in-vessel components such as breeding blanket and divertor, which are utilized in high-temperature and high-pressure water, and the recent progress of corrosion test apparatus simulating the unique environment of a fusion reactor will also be presented.

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Status and issues of high-temperature and high-pressure water corrosion research of fusion structural materials in Japanese DEMO reactor development

Nakajima,

Nozawa

2024

Nucl. Fusion

View full text Add to dashboard Cite

show abstract

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Early-stage aqueous corrosion-related defects in heavy ion irradiated P92 ferritic/martensitic alloy

Cited by 1 publication

References 48 publications

Status and issues of high-temperature and high-pressure water corrosion research of fusion structural materials in Japanese DEMO reactor development

Status and issues of high-temperature and high-pressure water corrosion research of fusion structural materials in Japanese DEMO reactor development

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