Microstructure and mechanical properties of friction stir weld performed on neutron-irradiated 304L steel with helium

Gussev, M. N.; Tang, W.; Chen, X.; Dixon, J. T.; Rosseel, T. M.

doi:10.1016/j.matchar.2024.113697

Microstructure and mechanical properties of friction stir weld performed on neutron-irradiated 304L steel with helium

Journal Article · Thu Feb 01 00:00:00 EST 2024 · Materials Characterization

DOI:https://doi.org/10.1016/j.matchar.2024.113697· OSTI ID:2301627

Gussev, M. N. ^[1]; Tang, W. ^[1]; Chen, X. ^[1]; Dixon, J. T. ^[1]; Rosseel, T. M. ^[1]

Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

As nuclear power plants (NPPs) approach or exceed 40–60 years of service, it may become necessary to repair damaged neutron-irradiated components to prolong longevity. However, fusion welding repair of irradiated steels and metallic materials is challenging because of helium-induced cracking. This study used friction stir welding (FSW) to address helium-related issues, such as helium bubble formation and grain boundary cracking. The microstructure, helium-induced degradation, and mechanical properties of a friction stir weld produced on neutron-irradiated 304L stainless steel with approximately 5.2 appm of helium were characterized. The analysis focused on variations in grain size, texture, and the morphology of helium-induced damage in the friction stir weld. Mechanical properties were characterized on the irradiated base metal (BM) and metallurgical zones of the friction stir weld: the stir zone (SZ), the thermo-mechanically affected zone (TMAZ), and the heat affected zone (HAZ). Only minor scattered porosity in the SZ and TMAZ and a few short microcracks (below 20 μm in length) in the TMAZ were observed, indicating limited helium-induced degradation. Tensile tests revealed good mechanical properties and fractography analysis demonstrated predominantly ductile fracture. In conclusion, the results highlight the immediate and substantial benefits of the FSW approach for repairing or joining helium-containing irradiated materials in NPPs.

View Accepted Manuscript (DOE)

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

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 2301627

Journal Information:: Materials Characterization, Journal Name: Materials Characterization Journal Issue: 2 Vol. 209; ISSN 1044-5803

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (37)

A possible solution of the problem of helium embrittlement Kesternich, W. Journal of Nuclear Materials, Vol. 127, Issue 2-3 https://doi.org/10.1016/0022-3115(85)90350-2	journal	January 1985
Metallographic analysis of helium-embrittlement cracking of repair welds in nuclear reactor tanks Kanne, W. R.; Lohmeier, D. A.; Dunn, K. A. Materials Characterization, Vol. 30, Issue 1 https://doi.org/10.1016/1044-5803(93)90005-G	journal	January 1993
Effect of weld thermal cycle, stress and helium content on helium bubble formation in stainless steels Kawano, S.; Kano, F.; Kinoshita, C. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01203-5	journal	December 2002
Weldability of neutron irradiated austenitic stainless steels Asano, Kyoichi; Nishimura, Seiji; Saito, Yoshiaki Journal of Nuclear Materials, Vol. 264, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00491-7	journal	January 1999
Study of grain boundary character along intergranular stress corrosion crack paths in austenitic alloys Gertsman, V. Y.; Bruemmer, S. M. Acta Materialia, Vol. 49, Issue 9 https://doi.org/10.1016/S1359-6454(01)00064-7	journal	May 2001
Very high swelling and embrittlement observed in a Fe–18Cr–10Ni–Ti hexagonal fuel wrapper irradiated in the BOR-60 fast reactor Neustroev, V. S.; Garner, F. A. Journal of Nuclear Materials, Vol. 378, Issue 3 https://doi.org/10.1016/j.jnucmat.2008.06.036	journal	September 2008
Study by EELS of helium bubbles in a martensitic steel Fréchard, S.; Walls, M.; Kociak, M. Journal of Nuclear Materials, Vol. 393, Issue 1 https://doi.org/10.1016/j.jnucmat.2009.05.011	journal	August 2009
Surface cracking on Σ3, Σ9 CSL and random grain boundaries in helium implanted 316L austenitic stainless steel Sakaguchi, N.; Ohguchi, Y.; Shibayama, T. Journal of Nuclear Materials, Vol. 432, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.08.019	journal	January 2013
In situ SEM-EBSD analysis of plastic deformation mechanisms in neutron-irradiated austenitic steel Gussev, M. N.; Leonard, K. J. Journal of Nuclear Materials, Vol. 517 https://doi.org/10.1016/j.jnucmat.2019.01.034	journal	April 2019
Effects of post-irradiation annealing on the IASCC susceptibility of neutron-irradiated 304L stainless steel Hesterberg, Justin; Jiao, Zhijie; Was, Gary S. Journal of Nuclear Materials, Vol. 526 https://doi.org/10.1016/j.jnucmat.2019.151755	journal	December 2019
Microstructure analysis of laser beam weldments performed on neutron-irradiated 304L steel containing 3 and 8 appm helium Gussev, M. N.; Zhong, W.; Garner, F. A. Journal of Nuclear Materials, Vol. 563 https://doi.org/10.1016/j.jnucmat.2022.153638	journal	May 2022
Microstructure and corrosion behavior of multipass gas tungsten arc welded 304L stainless steel Mirshekari, G. R.; Tavakoli, E.; Atapour, M. Materials & Design, Vol. 55 https://doi.org/10.1016/j.matdes.2013.10.064	journal	March 2014
Microstructural evolution and mechanical properties of friction stir welded joint of Fe–Cr–Mn–Mo–N austenite stainless steel Wang, D.; Ni, D. R.; Xiao, B. L. Materials & Design, Vol. 64 https://doi.org/10.1016/j.matdes.2014.07.063	journal	December 2014
Defect tolerance of friction stir welds in DH36 steel Stevenson, Ryan; Toumpis, Athanasios; Galloway, Alexander Materials & Design, Vol. 87 https://doi.org/10.1016/j.matdes.2015.08.064	journal	December 2015
Machines and control systems for friction stir welding: A review Mendes, Nuno; Neto, Pedro; Loureiro, Altino Materials & Design, Vol. 90 https://doi.org/10.1016/j.matdes.2015.10.124	journal	January 2016
Mitigation of He embrittlement and swelling in nickel by dispersed SiC nanoparticles Huang, H. F.; Zhang, W.; De Los Reyes, M. Materials & Design, Vol. 90 https://doi.org/10.1016/j.matdes.2015.10.147	journal	January 2016
In-situ material flow pattern around probe during friction stir welding of austenitic stainless steel Liu, F. C.; Nelson, T. W. Materials & Design, Vol. 110 https://doi.org/10.1016/j.matdes.2016.07.147	journal	November 2016
Microstructural evolution and pitting corrosion behavior of friction stir welded joint of high nitrogen stainless steel Zhang, H.; Wang, D.; Xue, P. Materials & Design, Vol. 110 https://doi.org/10.1016/j.matdes.2016.08.048	journal	November 2016
A review of dynamic recrystallization phenomena in metallic materials Huang, K.; Logé, R. E. Materials & Design, Vol. 111 https://doi.org/10.1016/j.matdes.2016.09.012	journal	December 2016
Grain orientation statistics of grain-clusters and the propensity of multiple-twinning during grain boundary engineering Liu, Tingguang; Xia, Shuang; Wang, Baoshun Materials & Design, Vol. 112 https://doi.org/10.1016/j.matdes.2016.09.079	journal	December 2016
In-situ grain structure and texture evolution during friction stir welding of austenite stainless steel Liu, F. C.; Nelson, T. W. Materials & Design, Vol. 115 https://doi.org/10.1016/j.matdes.2016.11.066	journal	February 2017
Microstructure evolution and mechanical properties of friction stir welding super-austenitic stainless steel S32654 Li, Huabing; Yang, Shouxing; Zhang, Shucai Materials & Design, Vol. 118 https://doi.org/10.1016/j.matdes.2017.01.034	journal	March 2017
Heterogeneous structure-induced strength-ductility synergy by partial recrystallization during friction stir welding of a high-entropy alloy Lin, Po-Ting; Liu, Hung-Chi; Hsieh, Po-Ying Materials & Design, Vol. 197 https://doi.org/10.1016/j.matdes.2020.109238	journal	January 2021
Microstructure and microchemistry of laser welds of irradiated austenitic steels Mao, Keyou S.; French, Aaron J.; Liu, Xiang Materials & Design, Vol. 206 https://doi.org/10.1016/j.matdes.2021.109764	journal	August 2021
Friction stir welding of SS 316 LN and Nitronic 50 jacket sections for application in superconducting fusion magnet systems Gaddam, Supreeth; Haridas, Ravi Sankar; Sanabria, Charlie Materials & Design, Vol. 221 https://doi.org/10.1016/j.matdes.2022.110949	journal	September 2022
Microstructure and mechanical properties of aluminum-steel dissimilar metal welded using arc and friction stir hybrid welding Liu, Ji; Wu, Bintao; Wang, Ziran Materials & Design, Vol. 225 https://doi.org/10.1016/j.matdes.2022.111520	journal	January 2023
Friction stir welding and processing Mishra, R. S.; Ma, Z. Y. Materials Science and Engineering: R: Reports, Vol. 50, Issue 1-2 https://doi.org/10.1016/j.mser.2005.07.001	journal	August 2005
Friction stir welding/processing of metals and alloys: A comprehensive review on microstructural evolution Heidarzadeh, A.; Mironov, S.; Kaibyshev, R. Progress in Materials Science, Vol. 117 https://doi.org/10.1016/j.pmatsci.2020.100752	journal	April 2021
Rapid formation of the sigma phase in 304 stainless steel during friction stir welding Park, Seung Hwan C.; Sato, Yutaka S.; Kokawa, Hiroyuki Scripta Materialia, Vol. 49, Issue 12 https://doi.org/10.1016/j.scriptamat.2003.08.022	journal	December 2003
Helium trapping at dislocations, precipitates and grain boundaries Kesternich, Wilto Radiation Effects, Vol. 78, Issue 1-4 https://doi.org/10.1080/00337578308207376	journal	January 1983
Evaluating the Potential for Remote In-Process Monitoring of Tool Wear in Friction Stir Welding of Stainless Steel Gibson, Brian T.; Tang, Wei; Peterson, Artie G. Journal of Manufacturing Science and Engineering, Vol. 140, Issue 2 https://doi.org/10.1115/1.4037242	journal	December 2017
A State-of-the-Art Review on Solid-State Metal Joining Cai, Wayne; Daehn, Glenn; Vivek, Anupam Journal of Manufacturing Science and Engineering, Vol. 141, Issue 3 https://doi.org/10.1115/1.4041182	journal	January 2019
Friction Stir Welding and Preliminary Characterization of Irradiated 304 Stainless Steel Tang, Wei; Gussev, Maxim; Feng, Zhili Volume 1: Codes and Standards https://doi.org/10.1115/PVP2019-93899	conference	July 2019
Grain boundary engineering: an overview after 25 years Randle, V. Materials Science and Technology, Vol. 26, Issue 3 https://doi.org/10.1179/026708309X12601952777747	journal	March 2010
Analysis of ferrite formed in 321 grade austenitic stainless steel Green, G.; Higginson, R.; Hogg, S. Materials Science and Technology, Vol. 31, Issue 4 https://doi.org/10.1179/1743284714Y.0000000564	journal	March 2015
Numerical modelling of 3D plastic flow and heat transfer during friction stir welding of stainless steel Nandan, R.; Roy, G. G.; Lienert, T. J. Science and Technology of Welding and Joining, Vol. 11, Issue 5 https://doi.org/10.1179/174329306X107692	journal	September 2006
Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels Hojná, Anna Metals, Vol. 7, Issue 10 https://doi.org/10.3390/met7100392	journal	September 2017

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