Irradiation-assisted cracking of SA508-304L weldments with 308L groove filler and 309L butter in hot water immersion constant rate extension tests

Heuser, Brent J.; Li, Zhen; Bai, Xian-Ming; Zhong, Weicheng; Sutton, Benjamin J.

doi:10.1016/j.jnucmat.2023.154472

Irradiation-assisted cracking of SA508-304L weldments with 308L groove filler and 309L butter in hot water immersion constant rate extension tests

Journal Article · Thu Apr 20 04:00:00 EDT 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154472· OSTI ID:2000349

Heuser, Brent J. ^[1]; Li, Zhen ^[1]; Bai, Xian-Ming ^[2]; ^[3]; Sutton, Benjamin J. ^[4]

University of Illinois, Urbana, IL (United States)
Virginia Polytechnic Institute and State University (Virginia Tech), Blacksburg, VA (United States)
University of Illinois, Urbana, IL (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Electric Power Research Institute, Charlotte, NC (United States)

Low alloy SA508 bainitic steel is often welded to 300 series austenitic stainless steel in nuclear power plants. These dissimilar metal weldments use 309L butter applied to the low alloy steel and 308L groove filler material to join the 309L to austenite. High alloy steels (such as the 308L and 309L material used here) have been identified as having greater susceptibility to irradiation-assisted stress corrosion cracking (IASCC). Evidence is presented here of cracking under tensile loads in 309L weldment butter in LWR hydrothermal conditions that correlates irradiation induced changes at δ ferrite–γ austenite phase boundaries and γ–γ grain boundaries; specifically intergranular Cr₂₃C₆ precipitates. Cracking is not observed in irradiated 308L groove filler under the same conditions. Both the 309L butter and 308L filler material have a duplex or mixed δ–γ phase microstructure due to solidification during the welding procedure. We have performed constant extension rate autoclave immersion tests in BWR normal water chemistry hot water (288 °C, 10 MPa, 2000 wt. ppb dissolved oxygen, <100 nS/cm conductivity, neutral pH) of proton irradiated (2 MeV, approximately 3 displacements per atom at a depth of 10 μm) tensile specimens. Proton irradiation to the dpa levels used here induced Cr₂₃C₆ carbide precipitation at γ–γ grain boundaries and δ–γ phase boundaries in the 309L butter but not the 308L filler. Cracking was observed in the proton-irradiated volume of 309L at these interfaces in the vicinity of the Cr₂₃C₆ precipitates. We hypothesis the SA508 is the source of carbon in the 309L butter. Cr depletion at γ–γ grain boundaries was also observed and may also be a root cause of cracking. Furthermore, the 309L butter is under significant tensile residual stress in the weldment that adds to applied tensile loads and this too may be a contributing factor.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: AC05-00OR22725; NE0008699

OSTI ID:: 2000349

Alternate ID(s):: OSTI ID: 1971158

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 1 Vol. 581; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (27)

Welding Metallurgy Kou, Sindo https://doi.org/10.1002/0471434027	book	October 2002
Microstructure, Hardness, and Residual Stress of the Dissimilar Metal Weldments of SA508-309L/308L-304L Zhong, Weicheng; Lin, Jun-Li; Chen, Yan Metallurgical and Materials Transactions A, Vol. 52, Issue 5 https://doi.org/10.1007/s11661-021-06203-x	journal	March 2021
Radiation-induced segregation in binary and ternary alloys Okamoto, P. R.; Rehn, L. E. Journal of Nuclear Materials, Vol. 83, Issue 1 https://doi.org/10.1016/0022-3115(79)90587-7	journal	August 1979
A theory of radiation-induced segregation in concentrated alloys Wiedersich, H.; Okamoto, P. R.; Lam, N. Q. Journal of Nuclear Materials, Vol. 83, Issue 1 https://doi.org/10.1016/0022-3115(79)90596-8	journal	August 1979
Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels Maziasz, P. J. Journal of Nuclear Materials, Vol. 169 https://doi.org/10.1016/0022-3115(89)90525-4	journal	December 1989
Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel Zinkle, S. J.; Maziasz, P. J.; Stoller, R. E. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90128-L	journal	November 1993
Theory of transitions in dose dependence of radiation effects in structural alloys Mansur, L. K. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90130-Q	journal	November 1993
Theory and experimental background on dimensional changes in irradiated alloys Mansur, L. K. Journal of Nuclear Materials, Vol. 216 https://doi.org/10.1016/0022-3115(94)90009-4	journal	October 1994
A thermodynamic study of the chromium-carbon system Berkane, R.; Gachon, J. C.; Charles, J. Calphad, Vol. 11, Issue 4 https://doi.org/10.1016/0364-5916(87)90035-6	journal	October 1987
Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels Busby, J. T.; Was, G. S.; Kenik, E. A. Journal of Nuclear Materials, Vol. 302, Issue 1 https://doi.org/10.1016/S0022-3115(02)00719-5	journal	April 2002
Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels Jiao, Z.; Was, G. S. Acta Materialia, Vol. 59, Issue 3 https://doi.org/10.1016/j.actamat.2010.10.055	journal	February 2011
Quantitative linkage between the stress at dislocation channel – Grain boundary interaction sites and irradiation assisted stress corrosion crack initiation Johnson, D. C.; Kuhr, B.; Farkas, D. Acta Materialia, Vol. 170 https://doi.org/10.1016/j.actamat.2019.02.032	journal	May 2019
Corrosion of phase and phase boundary in proton-irradiated 308L stainless steel weld metal in simulated PWR primary water Lin, Xiaodong; Peng, Qunjia; Mei, Jinna Corrosion Science, Vol. 165 https://doi.org/10.1016/j.corsci.2019.108401	journal	April 2020
Effect of post-irradiation annealing on microstructure and corrosion of proton-irradiated 308L stainless steel weld metal Lin, Xiaodong; Han, En-Hou; Peng, Qunjia Corrosion Science, Vol. 175 https://doi.org/10.1016/j.corsci.2020.108887	journal	October 2020
A high-resolution characterization of irradiation-assisted stress corrosion cracking of proton-irradiated 316L stainless steel in simulated pressurized water reactor primary water Kuang, Wenjun; Feng, Xingyu; Du, Donghai Corrosion Science, Vol. 199 https://doi.org/10.1016/j.corsci.2022.110187	journal	May 2022
Impact of localized deformation on IASCC in austenitic stainless steels Jiao, Z.; Was, G. S. Journal of Nuclear Materials, Vol. 408, Issue 3 https://doi.org/10.1016/j.jnucmat.2010.10.087	journal	January 2011
A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels Chopra, O. K.; Rao, A. S. Journal of Nuclear Materials, Vol. 409, Issue 3 https://doi.org/10.1016/j.jnucmat.2010.12.001	journal	February 2011
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys Was, Gary S.; Wharry, Janelle P.; Frisbie, Brian Journal of Nuclear Materials, Vol. 411, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.01.031	journal	April 2011
Comparison of the microstructure, deformation and crack initiation behavior of austenitic stainless steel irradiated in-reactor or with protons Stephenson, Kale J.; Was, Gary S. Journal of Nuclear Materials, Vol. 456 https://doi.org/10.1016/j.jnucmat.2014.08.021	journal	January 2015
Irradiation response of delta ferrite in as-cast and thermally aged cast stainless steel Li, Zhangbo; Lo, Wei-Yang; Chen, Yiren Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.08.006	journal	November 2015
A historical perspective on understanding IASCC Andresen, Peter L.; Was, Gary S. Journal of Nuclear Materials, Vol. 517 https://doi.org/10.1016/j.jnucmat.2019.01.057	journal	April 2019
Modified microstructures in proton irradiated dual phase 308L weldment filler material Li, Zhen; Zhan, Xun; Bai, Xian-Ming Journal of Nuclear Materials, Vol. 548 https://doi.org/10.1016/j.jnucmat.2021.152825	journal	May 2021
An examination of the precipitation behavior of proton irradiated dual phase 308L weldment filler materials Li, Zhen; Zhan, Xun; Swiech, Waclaw Journal of Nuclear Materials, Vol. 577 https://doi.org/10.1016/j.jnucmat.2023.154287	journal	April 2023
On the use of SRIM for computing radiation damage exposure Stoller, R. E.; Toloczko, M. B.; Was, G. S. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 310 https://doi.org/10.1016/j.nimb.2013.05.008	journal	September 2013
Role of irradiated microstructure and microchemistry in irradiation-assisted stress corrosion cracking Was *, G. S.; Busby, J. T. Philosophical Magazine, Vol. 85, Issue 4-7 https://doi.org/10.1080/02678370412331320224	journal	February 2005
Microstructural development and solidification cracking susceptibility of austenitic stainless steel welds Brooks, J. A.; Thompson, A. W. International Materials Reviews, Vol. 36, Issue 1 https://doi.org/10.1179/imr.1991.36.1.16	journal	January 1991
Stress Corrosion Cracking Behavior of Alloys in Aggressive Nuclear Reactor Core Environments Was, G. S.; Andresen, P. L. CORROSION, Vol. 63, Issue 1 https://doi.org/10.5006/1.3278331	journal	January 2007

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