TY - JOUR
T1 - Mechanical behavior of high-Ni/high-Mn Barsebäck 2 reactor pressure vessel welds after 28 years of operation
AU - Lindqvist, Sebastian
AU - Norrgård, Alex
AU - Arffman, Pentti
AU - Hytönen, Noora
AU - Lydman, Jari
AU - Efsing, Pål
AU - Suman, Siddharth
AU - Nevasmaa, Pekka
N1 - BRUTE (Barsebäck RPV material used for true evaluation of Embrittlement) is an Excellence project in the SAFIR2022 program, which is funded by VYR (Nuclear Waste Management Fund in Finland), VTT Technical Research Centre of Finland and NKS (Nordisk Kärnsäkerhet). The amount of in-kind contribution from the BREDA (Barsebäck Research & Development Arena) project is substantial as BREDA has planned, funded and executed the cutting of the trepans used in BRUTE. Thank you also to Jenny Roudén, Vattenfall, for technical discussions. The funding, access to plant relevant material and support from the supporting organizations is highly appreciated.
PY - 2023/8/1
Y1 - 2023/8/1
N2 - To assess long-term operation of the reactor pressure vessel (RPV), surveillance programs are applied for periodic monitoring and prediction of the aging of the mechanical properties due to irradiation and thermal embrittlement. In literature, there are limited data sets to compare the results from the surveillance program to the aging of the RPV. In this work, the tensile and impact toughness properties of the high-Ni, high-Mn welds from decommissioned Barsebäck 2 RPV are characterized. The results indicate that the surveillance program describes sufficiently the aging of the RPV welds. Differences in mechanical properties of the welds from various regions are explained by variations in post-weld heat treatment. The synergetic effect of Ni and Mn on embrittlement appears not to result at low fluences in a significant difference in the embrittlement rate when compared to ASTM E900 embrittlement trend curve prediction.
AB - To assess long-term operation of the reactor pressure vessel (RPV), surveillance programs are applied for periodic monitoring and prediction of the aging of the mechanical properties due to irradiation and thermal embrittlement. In literature, there are limited data sets to compare the results from the surveillance program to the aging of the RPV. In this work, the tensile and impact toughness properties of the high-Ni, high-Mn welds from decommissioned Barsebäck 2 RPV are characterized. The results indicate that the surveillance program describes sufficiently the aging of the RPV welds. Differences in mechanical properties of the welds from various regions are explained by variations in post-weld heat treatment. The synergetic effect of Ni and Mn on embrittlement appears not to result at low fluences in a significant difference in the embrittlement rate when compared to ASTM E900 embrittlement trend curve prediction.
KW - Embrittlement
KW - High-Ni/Mn weld
KW - Impact toughness
KW - Mechanical properties
KW - Strength
KW - Surveillance
KW - Transition temperature
UR - http://www.scopus.com/inward/record.url?scp=85153533656&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2023.154447
DO - 10.1016/j.jnucmat.2023.154447
M3 - Article
SN - 0022-3115
VL - 581
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 154447
ER -