TY - JOUR
T1 - Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors
AU - Gong, Xing
AU - Short, Michael P.
AU - Auger, Thierry
AU - Charalampopoulou, Evangelia
AU - Lambrinou, Konstantina
N1 - Funding Information:
X. Gong gratefully acknowledges the support of National Natural Science Foundation of China , China (Grant no. 51801129 and U21B2066 ). M.P. Short gratefully acknowledges the support of the U.S. Department of Energy ’s Nuclear Energy University Program (NEUP), under Grant No. DE-NE0008871 , United States. K. Lambrinou and E. Charalampopoulou gratefully acknowledge the support of the MYRRHA project that is currently ongoing at SCK CEN , Belgium. This review is in direct alignment with the interests of the EERA (European Energy Research Alliance) Joint Programme on Nuclear Materials (JPNM).
Funding Information:
X. Gong gratefully acknowledges the support of National Natural Science Foundation of China, China (Grant no. 51801129 and U21B2066). M.P. Short gratefully acknowledges the support of the U.S. Department of Energy's Nuclear Energy University Program (NEUP), under Grant No. DE-NE0008871, United States. K. Lambrinou and E. Charalampopoulou gratefully acknowledge the support of the MYRRHA project that is currently ongoing at SCK CEN, Belgium. This review is in direct alignment with the interests of the EERA (European Energy Research Alliance) Joint Programme on Nuclear Materials (JPNM).
Publisher Copyright:
© 2022 Elsevier Ltd
PY - 2022/5/1
Y1 - 2022/5/1
N2 - Liquid lead (Pb)- and lead–bismuth eutectic (LBE)-cooled fast neutron reactors (Gen-IV LFRs) are one of the most technologically mature fission reactor technologies, due to their inherent safety, high power density, and ability to burn nuclear waste. Accelerator-driven systems (ADS), in particular, promise to address the issues of long-lived radiotoxic nuclear waste, emerging uranium ore shortages, and the ever-increasing demand for energy. However, the conditional compatibility of conventional structural materials, such as steels, with liquid Pb and liquid LBE is still an important concern for the deployment of these advanced nuclear reactor systems, making the environmental degradation of candidate structural and fuel cladding steels the main impediment to the construction of Gen-IV LFRs, including ADS. This article presents a comprehensive review of the current understanding of environmental degradation of materials in contact with liquid Pb and liquid LBE, with a focus on the underlying mechanisms and the factors affecting liquid metal corrosion (LMC) and liquid metal embrittlement (LME), which are the two most important materials degradation effects. Moreover, this article addresses the most promising LMC and LME mitigation approaches, which aim to suppress their adverse influence on materials performance. An outlook of the needed future work in this field is also provided.
AB - Liquid lead (Pb)- and lead–bismuth eutectic (LBE)-cooled fast neutron reactors (Gen-IV LFRs) are one of the most technologically mature fission reactor technologies, due to their inherent safety, high power density, and ability to burn nuclear waste. Accelerator-driven systems (ADS), in particular, promise to address the issues of long-lived radiotoxic nuclear waste, emerging uranium ore shortages, and the ever-increasing demand for energy. However, the conditional compatibility of conventional structural materials, such as steels, with liquid Pb and liquid LBE is still an important concern for the deployment of these advanced nuclear reactor systems, making the environmental degradation of candidate structural and fuel cladding steels the main impediment to the construction of Gen-IV LFRs, including ADS. This article presents a comprehensive review of the current understanding of environmental degradation of materials in contact with liquid Pb and liquid LBE, with a focus on the underlying mechanisms and the factors affecting liquid metal corrosion (LMC) and liquid metal embrittlement (LME), which are the two most important materials degradation effects. Moreover, this article addresses the most promising LMC and LME mitigation approaches, which aim to suppress their adverse influence on materials performance. An outlook of the needed future work in this field is also provided.
KW - Liquid Pb
KW - Liquid LBE
KW - Liquid metal corrosion
KW - Liquid metal embrittlement
KW - Structural materials
KW - Environmental degradation
UR - http://www.scopus.com/inward/record.url?scp=85124429683&partnerID=8YFLogxK
U2 - 10.1016/j.pmatsci.2022.100920
DO - 10.1016/j.pmatsci.2022.100920
M3 - Article
VL - 126
JO - Progress in Materials Science
JF - Progress in Materials Science
SN - 0079-6425
M1 - 100920
ER -