양성자 조사가 316 스테인리스강의 미세조직과 표면산화 특성에 미치는 영향
Effects of Proton Irradiation on the Microstructure and Surface Oxidation Characteristics of Type 316 Stainless Steel
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Austenitic 316 stainless steel was irradiated with protons accelerated by an energy of 2 MeV at 360 oC, thevarious defects induced by this proton irradiation were characterized with microscopic equipment. In ourobservations irradiation defects such as dislocations and micro-voids were clearly revealed. The typicalirradiation defects observed differed according to depth, indicating the evolution of irradiation defects followsthe characteristics of radiation damage profiles that depend on depth. Surface oxidation tests wereconducted under the simulated primary water conditions of a pressurized water reactor (PWR) to understandthe role irradiation defects play in surface oxidation behavior and also to investigate the resultantirradiation assisted stress corrosion cracking (IASCC) susceptibility that occurs after exposure to PWR primarywater. We found that Cr and Fe became depleted while Ni was enriched at the grain boundarybeneath the surface oxidation layer both in the non-irradiated and proton-irradiated specimens. However,the degree of Cr/Fe depletion and Ni enrichment was much higher in the proton-irradiated sample than inthe non-irradiated one owing to radiation-induced segregation and the irradiation defects. The microstructuraland microchemical changes induced by proton irradiation all appear to significantly increase the susceptibilityof austenitic 316 stainless steel to IASCC.
Abstract
Austenitic 316 stainless steel was irradiated with protons accelerated by an energy of 2 MeV at 360 oC, thevarious defects induced by this proton irradiation were characterized with microscopic equipment. In ourobservations irradiation defects such as dislocations and micro-voids were clearly revealed. The typicalirradiation defects observed differed according to depth, indicating the evolution of irradiation defects followsthe characteristics of radiation damage profiles that depend on depth. Surface oxidation tests wereconducted under the simulated primary water conditions of a pressurized water reactor (PWR) to understandthe role irradiation defects play in surface oxidation behavior and also to investigate the resultantirradiation assisted stress corrosion cracking (IASCC) susceptibility that occurs after exposure to PWR primarywater. We found that Cr and Fe became depleted while Ni was enriched at the grain boundarybeneath the surface oxidation layer both in the non-irradiated and proton-irradiated specimens. However,the degree of Cr/Fe depletion and Ni enrichment was much higher in the proton-irradiated sample than inthe non-irradiated one owing to radiation-induced segregation and the irradiation defects. The microstructuraland microchemical changes induced by proton irradiation all appear to significantly increase the susceptibilityof austenitic 316 stainless steel to IASCC.
참고문헌 (30)
- J. McKinley, , Proc. of the 16th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor (2013)
- R. Pathania, "Fontevraud 7", pp.26~ (2010)
- S.M Bruemmer, "Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals", Journal of Nuclear Materials, 274(3), pp.299~314 (1999), Elsevier BV[DOI]
- O.K. Chopra, "A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels", Journal of Nuclear Materials, 409(3), pp.235~256 (2011), Elsevier BV[DOI]
- Peter L. Andresen, "A historical perspective on understanding IASCC", Journal of Nuclear Materials, 517, pp.380~392 (2019), Elsevier BV[DOI]
- S. J. Zinkle, "Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations", Scripta Materialia, 143, pp.154~ (2018)[DOI]
- J Gan, "Microstructure evolution in austenitic Fe–Cr–Ni alloys irradiated with rotons: comparison with neutron-irradiated microstructures", Journal of Nuclear Materials, 297(2), pp.161~175 (2001), Elsevier BV[DOI]
- G.S Was, "Emulation of neutron irradiation effects with protons: validation of principle", Journal of Nuclear Materials, 300(2-3), pp.198~216 (2002), Elsevier BV[DOI]
- Bulent H. Sencer, "Proton irradiation emulation of PWR neutron damage microstructures in solution annealed 304 and cold-worked 316 stainless steels", Journal of Nuclear Materials, 323(1), pp.18~28 (2003), Elsevier BV[DOI]
- Kale J. Stephenson, "Comparison of the microstructure, deformation and crack initiation behavior of austenitic stainless steel irradiated in-reactor or with protons", Journal of Nuclear Materials, 456, pp.85~98 (2015), Elsevier BV[DOI]
- J. F. Ziegler, "The Stopping and Range of Ions in Solids" (1985), Pergamon
- D.J Edwards, "Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 °C", Journal of Nuclear Materials, 317(1), pp.13~31 (2003), Elsevier BV[DOI]
- Zheng-cao Li, "Analysis of Defects Formation and Mobility during Ion Irradiation by Coherent Precipitates", MATERIALS TRANSACTIONS, 47(2), pp.259~262 (2006), Japan Institute of Metals[DOI]
- Dongyue Chen, "Depth distribution of Frank loop defects formed in ion-irradiated stainless steel and its dependence on Si addition", Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 365, pp.503~508 (2015), Elsevier BV[DOI]
- Lin Shao, "Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions", Journal of Nuclear Materials, 453(1-3), pp.176~181 (2014), Elsevier BV[DOI]
- C. Zheng, "Radiation-induced swelling and radiation-induced segregation & precipitation in dual beam irradiated Ferritic", Martensitic HT9 steel, 2017, pp.134, 152~162[DOI]
- R.E. Stoller, "On the use of SRIM for computing radiation damage exposure", Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 310, pp.75~80 (2013), Elsevier BV[DOI]
- R. E. Schramm, "Stacking fault energies of seven commercial austenitic stainless steels, 316 SS stacking fault energy", Metallurgical Transactions A, 6(7), pp.1345~1351 (1975), Springer Science and Business Media LLC[DOI]
- P. J. Brofman, "On the Effect of Carbon on the Stacking Fault Energy of Austenitic Stainless Steels", Metallurgical Transactions A, 9(6), pp.879~880 (1978), Springer Science and Business Media LLC[DOI]
- S. J. Zinkle, "Comprehensive Nuclear Materials, Vol. 1" (2012), Elsevier
- Ji-Jung Kai, "Effects of proton irradiation on the microstructural and microchemical evolution of Inconel 600 alloy", Journal of Nuclear Materials, 207, pp.286~294 (1993), Elsevier BV[DOI]
- Z. Jiao, "Deformation microstructure of proton-irradiated stainless steels", Journal of Nuclear Materials, 361(2-3), pp.218~227 (2007), Elsevier BV[DOI]
- Martina Meisnar, "A mechanistic study of the temperature dependence of the stress corrosion crack growth rate in SUS316 stainless steels exposed to PWR primary water", Acta Materialia, 114, pp.15~24 (2016), Elsevier BV[DOI]
- Karen Kruska, "Nanoscale characterisation of grain boundary oxidation in cold-worked stainless steels", Corrosion Science, 63, pp.225~233 (2012), Elsevier BV[DOI]
- Yun Soo Lim, "Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment", Corrosion Science, 108, pp.125~133 (2016), Elsevier BV[DOI]
- R. C. Newman, "Another Way to Think About the Critical Oxide Volume Fraction for the Internal-to-External Oxidation Transition?", Corrosion, 64, pp.721~ (2008)[DOI]
- S. M. Bruemmer, "Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals", Journal of Nuclear Materials, 274, pp.299~ (1999)[DOI]
- Y. S. Lim, , Transactions of the Korean Nuclear Society Spring Meeting (2019)
- V. Kain, "Testing Sensitization and Predicting Susceptibility to Intergranular Corrosion and Intergranular Stress Corrosion Cracking in Austenitic Stainless Steels", Corrosion, 58, pp.15~ (2002)[DOI]
- T. Fujii, "Analysis of the early stage of stress corrosion cracking in austenitic stainless steel by EBSD and XRD", Materials Characterization, 172, pp.110882~ (2021)[DOI]
