A critical review of irradiation-induced changes in reactor pressure vessel steels

Bohanon, Brandon; Wei, Peng; Foster, Ashley; Bazar, Layali; Zhang, Yongfeng; Spearot, Douglas; Bachhav, Mukesh; Capolungo, Laurent; Aitkaliyeva, Assel

doi:10.1016/j.pnucene.2024.105276

A critical review of irradiation-induced changes in reactor pressure vessel steels

Journal Article · Tue May 28 04:00:00 EDT 2024 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2024.105276· OSTI ID:2439978

Bohanon, Brandon ^[1]; Wei, Peng ^[2]; Foster, Ashley ^[1]; Bazar, Layali ^[1]; Zhang, Yongfeng ^[2]; Spearot, Douglas ^[1]; ^[3]; Capolungo, Laurent ^[4]; ^[1]

Univ. of Florida, Gainesville, FL (United States)
Univ. of Wisconsin, Madison, WI (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

A large body of work has been conducted to investigate the embrittlement and degradation of reactor pressure vessel (RPV) steels. This includes experiments on alloys with different compositions, performed in research and test reactors and ion accelerators that span various temperatures, fluxes, and fluences. In this paper, we perform a critical review of the published experimental data and compile experimentally reported values for dislocation loop size/density, precipitate size/density and yield stress into an easily downloadable format that can be used by both experimentalists and modelers. This thorough experimental review is complemented by a brief review of simulation efforts at atomistic and mesoscopic length scales. Finally, this paper highlights key aspects of the behavior of RPV steels under irradiation, identifies gaps or discrepancies in current understanding, and identifies priority future research directions.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2439978

Alternate ID(s):: OSTI ID: 2367435
OSTI ID: 2472439
OSTI ID: 2564702

Report Number(s):: INL/JOU--24-76508-Rev000

Journal Information:: Progress in Nuclear Energy, Journal Name: Progress in Nuclear Energy Vol. 174; ISSN 0149-1970

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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A critical review of irradiation-induced changes in reactor pressure vessel steels

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