Effects of Radiation-Induced Defects on Corrosion

Schmidt, Franziska; Hosemann, Peter; Scarlat, Raluca O.; Schreiber, Daniel K.; Scully, John R.; Uberuaga, Blas P.

doi:10.1146/annurev-matsci-080819-123403

Title: Effects of Radiation-Induced Defects on Corrosion

Journal Article · 25 July 2021 · Annual Review of Materials Research

DOI: https://doi.org/10.1146/annurev-matsci-080819-123403 · OSTI ID:1830581

Schmidt, Franziska ^[1]; Hosemann, Peter ^[2]; Scarlat, Raluca O. ^[2]; Schreiber, Daniel K. ^[3]; Scully, John R. ^[4];

^[5]

Univ. of California, Berkeley, CA (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Univ. of California, Berkeley, CA (United States)
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Univ. of Virginia, Charlottesville, VA (United States)
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

The next generation of nuclear reactors will expose materials to conditions that, in some cases, are even more extreme than those in current fission reactors, inevitably leading to new materials science challenges. Radiation-induced damage and corrosion are two key phenomena that must be understood both independently and synergistically, but their interactions are often convoluted. In the light water reactor community, a tremendous amount of work has been done to illuminate irradiation-corrosion effects, and similar efforts are under way for heavy liquid metal and molten salt environments. While certain effects, such as radiolysis and irradiation-assisted stress corrosion cracking, are reasonably well established, the basic science of how irradiation-induced defects in the base material and the corrosion layer influence the corrosion process still presents many unanswered questions. In this review, we summarize the work that has been done to understand these coupled extremes, highlight the complex nature of this problem, and identify key knowledge gaps.

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Research Organization:: Energy Frontier Research Centers (EFRC) (United States). Fundamental Understanding of Transport Under Reactor Extremes (FUTURE); Los Alamos National Laboratory (LANL)

Sponsoring Organization:: USDOE Office of Science (SC). Basic Energy Sciences (BES)

Grant/Contract Number:: 89233218CNA000001; AC05-76RL01830

OSTI ID:: 1830581

Report Number(s):: LA-UR--20-27575

Journal Information:: Annual Review of Materials Research, Journal Name: Annual Review of Materials Research Journal Issue: 1 Vol. 51; ISSN 1531-7331

Publisher:: Annual ReviewsCopyright Statement

Country of Publication:: United States

Language:: English

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A Review of Recent Advances in the Understanding of Liquid Metal Embrittlement Kolman, David G. CORROSION, Vol. 75, Issue 1 https://doi.org/10.5006/2904	journal	January 2019
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Role of Cavity Formation on Long-Term Stress Corrosion Cracking Initiation: A Review Arioka, Koji Corrosion, Vol. 76, Issue 2 https://doi.org/10.5006/3374	journal	November 2019