TY - GEN
T1 - BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2
AU - Arffman, Pentti
AU - Lydman, Jari
AU - Hytönen, Noora
AU - Que, Zaiqing
AU - Lindqvist, Sebastian
N1 - Funding Information:
BRUTE is a project in the SAFIR2022 program. It is funded by VYR (Nuclear Waste Management Fund), VTT Technical Research Centre of Finland and NKS (Nordisk Kärnsäkerhet). Furthermore, the objectives of BRUTE are set out in the Nordic BREDA (Barsebäck Research & Development Arena) project. The contributions of BREDA are substantial, as it has also planned and executed the cutting of the trepans used in BRUTE from the pressure vessel, among others. Also, the scientific support and background information provided by the Swedish stakeholders from Energiforsk, Ringhals, Forsmark and OKG have been significant in the success of the project. The funding, materials and technical support are all greatly appreciated.
Publisher Copyright:
© 2022 American Society of Mechanical Engineers (ASME). All rights reserved.
PY - 2022/11/4
Y1 - 2022/11/4
N2 - Project BRUTE has investigated weld materials extracted from the decommissioned Barseback 2 reactor pressure vessel. The materials investigated originate from the pressure vessel head (RPVH) and beltline regions. The performed mechanical testing include tensile, Charpy impact and fracture toughness testing. Tensile testing with miniature specimens demonstrates a difference of over 50 MPa in the yield and ultimate tensile strengths of the RPVH and beltline materials. Beltline specimens tested at the operating temperature exhibit discontinuity past the yield region, possibly indicating dynamic strain aging. Charpy impact tests were performed around the transition region of the material. Transition curves were fitted, and reference temperatures T28J of-85 C and-106 C were determined for RPVH and beltline materials, respectively. This indicates better material properties at beltline compared to the RPVH, in agreement with tensile results. The reference temperatures T28J were further utilized to estimate brittle fracture initiation toughness reference temperatures T0. Fracture toughness testing follows the Master Curve methodology defined in ASTM standard E1921. Reference temperatures T0 were determined at-115.1 C and-101.1 C for the RPVH and beltline, respectively, but the tests indicate inhomogeneity in both materials. The mean reference temperatures of the multimodal models TM were determined at-110.0 C and-96.5 C, and the associated, margin adjusted lower confidence bounds TM5%, MA at-13.3 C and-53.0 C for the RPVH and beltline materials, respectively. The latter values indicate that the inhomogeneity is more extensive in the RPVH. The estimates obtained from the Charpy impact toughness results do not correlate consistently with the fracture toughnessbased transition temperature, possibly due to the inhomogeneity of the materials. The results show that the safety of the materials can be assessed reliably, provided that contemporary methods, equipment and analyses are used.
AB - Project BRUTE has investigated weld materials extracted from the decommissioned Barseback 2 reactor pressure vessel. The materials investigated originate from the pressure vessel head (RPVH) and beltline regions. The performed mechanical testing include tensile, Charpy impact and fracture toughness testing. Tensile testing with miniature specimens demonstrates a difference of over 50 MPa in the yield and ultimate tensile strengths of the RPVH and beltline materials. Beltline specimens tested at the operating temperature exhibit discontinuity past the yield region, possibly indicating dynamic strain aging. Charpy impact tests were performed around the transition region of the material. Transition curves were fitted, and reference temperatures T28J of-85 C and-106 C were determined for RPVH and beltline materials, respectively. This indicates better material properties at beltline compared to the RPVH, in agreement with tensile results. The reference temperatures T28J were further utilized to estimate brittle fracture initiation toughness reference temperatures T0. Fracture toughness testing follows the Master Curve methodology defined in ASTM standard E1921. Reference temperatures T0 were determined at-115.1 C and-101.1 C for the RPVH and beltline, respectively, but the tests indicate inhomogeneity in both materials. The mean reference temperatures of the multimodal models TM were determined at-110.0 C and-96.5 C, and the associated, margin adjusted lower confidence bounds TM5%, MA at-13.3 C and-53.0 C for the RPVH and beltline materials, respectively. The latter values indicate that the inhomogeneity is more extensive in the RPVH. The estimates obtained from the Charpy impact toughness results do not correlate consistently with the fracture toughnessbased transition temperature, possibly due to the inhomogeneity of the materials. The results show that the safety of the materials can be assessed reliably, provided that contemporary methods, equipment and analyses are used.
KW - ageing
KW - fracture
KW - reactor
KW - nuclear
KW - pressure vessel
KW - weld
KW - structural integrity
KW - Reactor/Nuclear
KW - Ageing
KW - Fracture
KW - Pressure Vessel
KW - Weld
KW - Structural Integrity
UR - http://www.scopus.com/inward/record.url?scp=85142420893&partnerID=8YFLogxK
U2 - 10.1115/PVP2022-83819
DO - 10.1115/PVP2022-83819
M3 - Conference article in proceedings
VL - 4A
BT - ASME 2022 Pressure Vessels and Piping Conference
PB - American Society of Mechanical Engineers (ASME)
T2 - ASME 2022 Pressure Vessels and Piping Conference, PVP 2022
Y2 - 17 July 2022 through 22 July 2022
ER -