TY - JOUR
T1 - Microstructural changes of a thermally aged stainless steel submerged arc weld overlay cladding of nuclear reactor pressure vessels
AU - Takeuchi, T.
AU - Kameda, J.
AU - Nagai, Y.
AU - Toyama, T.
AU - Matsukawa, Y.
AU - Nishiyama, Y.
AU - Onizawa, K.
N1 - Funding Information:
This study was carried out under the Cooperative Research Program of International Research Center for Nuclear Materials Science, Institute for Materials Research (IMR), Tohoku University. A part of this study was the result of “Study of degradation mechanism of stainless steel weld overlay cladding of nuclear reactor pressure vessels” carried out under the Strategic Promotion Program for Basic Nuclear Research by the Ministry of Education, Culture, Sports, Science and Technology of Japan. This study was partially supported by Grant-in-Aid for Scientific Research (A) (21246142) of the Ministry of Education, Culture, Sports, Science and Technology (MEXT) and by the Budget for Nuclear Research of the Ministry of Education, Culture, Sports, Science and Technology, based on the screening and counseling by the Atomic Energy Commission.
PY - 2012/6
Y1 - 2012/6
N2 - The effect of thermal aging on microstructural changes in stainless steel submerged arc weld-overlay cladding of reactor pressure vessels was investigated using atom probe tomography (APT). In as-received materials subjected to post-welding heat treatments (PWHTs), with a subsequent furnace cooling, a slight fluctuation of the Cr concentration was observed due to spinodal decomposition in the δ-ferrite phase but not in the austenitic phase. Thermal aging at 400°C for 10,000 h caused not only an increase in the amplitude of spinodal decomposition but also the precipitation of G phases with composition ratios of Ni:Si:Mn = 16:7:6 in the δ-ferrite phase. The degree of the spinodal decomposition in the submerged arc weld sample was similar to that in the electroslag weld one reported previously. We also observed a carbide on the γ-austenite and δ-ferrite interface. There were no Cr depleted zones around the carbide.
AB - The effect of thermal aging on microstructural changes in stainless steel submerged arc weld-overlay cladding of reactor pressure vessels was investigated using atom probe tomography (APT). In as-received materials subjected to post-welding heat treatments (PWHTs), with a subsequent furnace cooling, a slight fluctuation of the Cr concentration was observed due to spinodal decomposition in the δ-ferrite phase but not in the austenitic phase. Thermal aging at 400°C for 10,000 h caused not only an increase in the amplitude of spinodal decomposition but also the precipitation of G phases with composition ratios of Ni:Si:Mn = 16:7:6 in the δ-ferrite phase. The degree of the spinodal decomposition in the submerged arc weld sample was similar to that in the electroslag weld one reported previously. We also observed a carbide on the γ-austenite and δ-ferrite interface. There were no Cr depleted zones around the carbide.
UR - http://www.scopus.com/inward/record.url?scp=84860436717&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84860436717&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2011.12.004
DO - 10.1016/j.jnucmat.2011.12.004
M3 - Article
AN - SCOPUS:84860436717
SN - 0022-3115
VL - 425
SP - 60
EP - 64
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1-3
ER -