Impact of Low-Temperature Neutron Irradiation on Tensile Behavior of Base Metal and Electron-Beam Welded 316L Stainless Steel

Silva, Chinthaka M.; Leonard, Keith J.; Garrison, Lauren M.; Bryan, Chris D.; Holliday, Kiel S.

doi:10.1007/s11661-022-06770-7

Impact of Low-Temperature Neutron Irradiation on Tensile Behavior of Base Metal and Electron-Beam Welded 316L Stainless Steel

Journal Article · Thu Aug 18 00:00:00 EDT 2022 · Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science

DOI:https://doi.org/10.1007/s11661-022-06770-7· OSTI ID:1887019

Silva, Chinthaka M. ^[1]; Leonard, Keith J. ^[2]; Garrison, Lauren M. ^[3]; Bryan, Chris D. ^[3]; Holliday, Kiel S. ^[4]

Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Torch Technologies, Shalimar, FL (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Here, a study of 316L type stainless steel in its base metal and electron-beam (e-beam) welded conditions was performed to observe the effects of low-temperature (60 °C to 100 °C) neutron irradiation on the tensile behavior of the samples. Fractography was used in understanding the tensile-tested fracture surfaces of the 316L samples in these different forms with the characterization of the both base metal and welded samples using electron microscopy. Irradiation of the tensile specimens made free of defects of cutting and mechanical polishing showed a reduction in their tensile ductility with increased radiation-induced hardening up to 1.40 × 10¹⁹ n/cm² (E > 0.1 MeV) fluence that corresponds to 1.1x 10^-2 dpa, even at the low irradiation temperatures. These low-temperature neutron irradiated base metal and e-beam welded 316L specimens also consisted of closely similar fracture surfaces characteristic of ductile rupture.

View Accepted Manuscript (DOE)

Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC52-07NA27344

OSTI ID:: 1887019

Report Number(s):: LLNL-JRNL-824520; 1038009

Journal Information:: Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science, Journal Name: Metallurgical and Materials Transactions. A, Physical Metallurgy and Materials Science Journal Issue: 10 Vol. 53; ISSN 1073-5623

Publisher:: ASM InternationalCopyright Statement

Country of Publication:: United States

Language:: English

References (24)

Sensitization evaluation of the austenitic stainless steel AISI 304L, 316L, 321 and 347 Lima, A. S.; Nascimento, A. M.; Abreu, H. F. G. Journal of Materials Science, Vol. 40, Issue 1 https://doi.org/10.1007/s10853-005-5699-9	journal	January 2005
Swelling as a consequence of gamma prime (γ') and M23(C, Si)6 formation in neutron irradiated 316 stainless steel Brager, H. R.; Garner, F. A. Journal of Nuclear Materials, Vol. 73, Issue 1 https://doi.org/10.1016/0022-3115(78)90474-9	journal	April 1978
Some effects of increased helium content on void formation and solute segregation in neutron irradiated type 316 stainless steel Maziasz, P. J. Journal of Nuclear Materials, Vol. 108-109 https://doi.org/10.1016/0022-3115(82)90505-0	journal	July 1982
Program of United states-Japan collaborative testing in HFIR and ORR Scott, J. L.; Grossbeck, M. L.; Hishinuma, A. Journal of Nuclear Materials, Vol. 141-143 https://doi.org/10.1016/0022-3115(86)90132-7	journal	November 1986
Post irradiation tensile and fatigue behavior of austenitic PCA stainless steels irradiated in HFIR Tanaka, M. P.; Hamada, S.; Hishinuma, A. Journal of Nuclear Materials, Vol. 155-157 https://doi.org/10.1016/0022-3115(88)90448-5	journal	July 1988
Fast neutron irradiation hardening of austenitic stainless steel at 250°C Elen, J. D.; Fenici, P. Journal of Nuclear Materials, Vol. 191-194 https://doi.org/10.1016/0022-3115(92)90575-6	journal	September 1992
Tensile properties of type 316L(N) stainless steel irradiated to 10 displacements per atom Horsten, M. G.; de Vries, M. I. Journal of Nuclear Materials, Vol. 212-215 https://doi.org/10.1016/0022-3115(94)90114-7	journal	September 1994
Tensile properties of candidate SNS target container materials after proton and neutron irradiation in the LANSCE accelerator Farrell, K.; Byun, T. S. Journal of Nuclear Materials, Vol. 296, Issue 1-3 https://doi.org/10.1016/S0022-3115(01)00515-3	journal	July 2001
Neutron irradiation effect on the mechanical properties of type 316L SS welded joints Saito, S.; Fukaya, K.; Ishiyama, S. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)01021-8	journal	December 2002
Comparison of fission neutron and proton/spallation neutron irradiation effects on the tensile behavior of type 316 and 304 stainless steel Maloy, S. A.; James, M. R.; Johnson, W. R. Journal of Nuclear Materials, Vol. 318 https://doi.org/10.1016/S0022-3115(03)00087-4	journal	May 2003
Influence of post-irradiation thermal annealing on the mechanical properties of ion irradiated layers in 316L stainless steel Robertson, C.; Boulanger, L.; Poissonnet, S. Journal of Nuclear Materials, Vol. 271-272 https://doi.org/10.1016/S0022-3115(98)00768-5	journal	May 1999
Austenitic Stainless Steels for Fast Reactors -Irradiation Experiments, Property Evaluation and Microstructural Studies Karthik, V.; Murugan, S.; Parameswaran, P. Energy Procedia, Vol. 7 https://doi.org/10.1016/j.egypro.2011.06.033	journal	January 2011
Effect of irradiation on the steels 316L/LN type to 12 dpa at 400 °C Bulanova, T.; Fedoseev, A.; Kalinin, G. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.099	journal	August 2004
Structural stability and hardness of carburized surfaces of 316 stainless steel after welding and after neutron irradiation Farrell, K.; Byun, T. S. Journal of Nuclear Materials, Vol. 356, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2006.05.027	journal	September 2006
Influence of LBE long term exposure and simultaneous fast neutron irradiation on the mechanical properties of T91 and 316L Stergar, E.; Eremin, S. G.; Gavrilov, S. Journal of Nuclear Materials, Vol. 473 https://doi.org/10.1016/j.jnucmat.2016.02.008	journal	May 2016
Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation Byun, T. S.; Garrison, B. E.; McAlister, M. R. Journal of Nuclear Materials, Vol. 548 https://doi.org/10.1016/j.jnucmat.2021.152849	journal	May 2021
Characterization of alloy 718 subjected to different thermomechanical treatments Silva, Chinthaka; Song, Miao; Leonard, Keith Materials Science and Engineering: A, Vol. 691 https://doi.org/10.1016/j.msea.2017.03.045	journal	April 2017
Characterization of different forms of Zr-2.5Nb samples before and after neutron irradiation Silva, Chinthaka; Leonard, Keith; Trammel, Michael Materials Science and Engineering: A, Vol. 716 https://doi.org/10.1016/j.msea.2018.01.059	journal	February 2018
Effects of low-temperature neutron irradiation on the microstructure and tensile properties of duplex 2304 stainless steel and its electron-beam welds Silva, Chinthaka M.; Leonard, Keith J.; Garrison, Lauren M. Materials Science and Engineering: A, Vol. 823 https://doi.org/10.1016/j.msea.2021.141780	journal	August 2021
Radiation-induced degradation of stainless steel light water reactor internals Kenik, Edward A.; Busby, Jeremy T. Materials Science and Engineering: R: Reports, Vol. 73, Issue 7-8 https://doi.org/10.1016/j.mser.2012.05.002	journal	July 2012
Fatigue Crack Growth Behavior of 316LN Stainless Steel with Different Nitrogen Contents Babu, M. Nani; Dutt, B. Shashank; Venugopal, S. Procedia Engineering, Vol. 55 https://doi.org/10.1016/j.proeng.2013.03.320	journal	January 2013
Radiation-induced swelling and hardening of 316L stainless steel fabricated by selected laser melting Lin, Jiwei; Chen, Feida; Tang, Xiaobin Vacuum, Vol. 174 https://doi.org/10.1016/j.vacuum.2020.109183	journal	April 2020
Effect of molybdenum additions on the microstructures and corrosion behaviours of 316L stainless steel-based alloys Rahman, T.; Ebert, W. L.; Indacochea, J. E. Corrosion Engineering, Science and Technology, Vol. 53, Issue 3 https://doi.org/10.1080/1478422X.2018.1443991	journal	February 2018
Materials issues in fusion reactors Suri, A. K.; Krishnamurthy, N.; Batra, I. S. Journal of Physics: Conference Series, Vol. 208 https://doi.org/10.1088/1742-6596/208/1/012001	journal	February 2010

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