TY - JOUR
T1 - Environmentally-assisted cracking behaviour in the transition region of an Alloy182/SA 508 Cl.2 dissimilar metal weld joint in simulated boiling water reactor normal water chemistry environment
AU - Seifert, H. P.
AU - Ritter, S.
AU - Shoji, T.
AU - Peng, Q. J.
AU - Takeda, Y.
AU - Lu, Z. P.
N1 - Funding Information:
The results of this paper were generated within a co-operation work between the Fracture & Reliability Research Institute (FRI) and Paul Scherrer Institute (PSI) and are a part of the PEACE-II/III (FRI) and RIKORR-II/KORA (PSI) programs. The financial support of the PEACE-II/III program by EdF, EPRI, Hitachi, JAPCO, KEPCO, MHI, SKI, Tohoku EPCO, TEPCO, TEPCO, Toshiba and IHI and of the RIKORR-II/KORA program by the Swiss Federal Nuclear Safety Inspectorate (HSK) and Swiss Federal Office for Energy (BFE) is gratefully acknowledged. Thanks are also expressed to B. Baumgartner, L. Nue, U. Ineichen, U. Tschanz, B. Gerodetti and E. Groth (all PSI) for their experimental contribution to this work.
PY - 2008/8/31
Y1 - 2008/8/31
N2 - The stress corrosion cracking (SCC) and corrosion fatigue behaviour perpendicular and parallel to the fusion line in the transition region between the Alloy 182 Nickel-base weld metal and the adjacent SA 508 Cl.2 low-alloy reactor pressure vessel (RPV) steel of a simulated dissimilar metal weld joint was investigated under boiling water reactor normal water chemistry conditions. A special emphasis was placed to the question whether a fast growing interdendritic SCC crack in the highly susceptible Alloy 182 weld metal can easily cross the fusion line and significantly propagate into the adjacent low-alloy RPV steel. Cessation of interdendritic SCC crack growth was observed in high-purity or sulphate-containing oxygenated water under constant or periodical partial unloading conditions for those parts of the crack front, which reached the fusion line. In chloride containing water, on the other hand, the interdendritic SCC crack in the Alloy 182 weld metal very easily crossed the fusion line and further propagated with a very high rate as a transgranular crack into the heat-affected zone and base metal of the adjacent low-alloy steel. The observed SCC cracking behaviour at the interface correlates excellently with the field experience of such dissimilar metal weld joints, where SCC cracking was usually confined to the Alloy 182 weld metal.
AB - The stress corrosion cracking (SCC) and corrosion fatigue behaviour perpendicular and parallel to the fusion line in the transition region between the Alloy 182 Nickel-base weld metal and the adjacent SA 508 Cl.2 low-alloy reactor pressure vessel (RPV) steel of a simulated dissimilar metal weld joint was investigated under boiling water reactor normal water chemistry conditions. A special emphasis was placed to the question whether a fast growing interdendritic SCC crack in the highly susceptible Alloy 182 weld metal can easily cross the fusion line and significantly propagate into the adjacent low-alloy RPV steel. Cessation of interdendritic SCC crack growth was observed in high-purity or sulphate-containing oxygenated water under constant or periodical partial unloading conditions for those parts of the crack front, which reached the fusion line. In chloride containing water, on the other hand, the interdendritic SCC crack in the Alloy 182 weld metal very easily crossed the fusion line and further propagated with a very high rate as a transgranular crack into the heat-affected zone and base metal of the adjacent low-alloy steel. The observed SCC cracking behaviour at the interface correlates excellently with the field experience of such dissimilar metal weld joints, where SCC cracking was usually confined to the Alloy 182 weld metal.
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U2 - 10.1016/j.jnucmat.2008.06.034
DO - 10.1016/j.jnucmat.2008.06.034
M3 - Article
AN - SCOPUS:48049100556
SN - 0022-3115
VL - 378
SP - 197
EP - 210
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 2
ER -