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

다국어 초록 (Multilingual Abstract)

Austenitic 316 stainless steel was irradiated with protons accelerated by an energy of 2 MeV at 360 ℃, the various defects induced by this proton irradiation were characterized with microscopic equipment. In our observations irradiation defects such as dislocations and micro-voids were clearly revealed. The typical irradiation defects observed differed according to depth, indicating the evolution of irradiation defects follows the characteristics of radiation damage profiles that depend on depth. Surface oxidation tests were conducted under the simulated primary water conditions of a pressurized water reactor (PWR) to understand the role irradiation defects play in surface oxidation behavior and also to investigate the resultant irradiation assisted stress corrosion cracking (IASCC) susceptibility that occurs after exposure to PWR primary water. We found that Cr and Fe became depleted while Ni was enriched at the grain boundary beneath 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 in the non-irradiated one owing to radiation-induced segregation and the irradiation defects. The microstructural and microchemical changes induced by proton irradiation all appear to significantly increase the susceptibility of austenitic 316 stainless steel to IASCC.

참고문헌 (Reference)

1 J. McKinley, 2013

2 Y. S. Lim, 2019

3 J. F. Ziegler, "The Stopping and Range of Ions in Solids" Pergamon 1985

4 V. Kain, "Testing Sensitization and Predicting Susceptibility to Intergranular Corrosion and Intergranular Stress Corrosion Cracking in Austenitic Stainless Steels" 58 : 15-, 2002

5 R. E. Schramm, "Stacking fault energies of seven commercial austenitic stainless steels, 316 SS stacking fault energy" Springer Science and Business Media LLC 6 (6): 1345-1351, 1975

6 C. Zheng, "Radiation-induced swelling and radiation-induced segregation & precipitation in dual beam irradiated Ferritic/Martensitic HT9 steel" Elsevier BV 134 : 152-162, 2017

7 S.M Bruemmer, "Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals" Elsevier BV 274 (274): 299-314, 1999

8 S. M. Bruemmer, "Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals" 274 : 299-, 1999

9 Bulent H. Sencer, "Proton irradiation emulation of PWR neutron damage microstructures in solution annealed 304 and cold-worked 316 stainless steels" Elsevier BV 323 (323): 18-28, 2003

10 S. J. Zinkle, "Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations" 143 : 154-, 2018

11 R.E. Stoller, "On the use of SRIM for computing radiation damage exposure" Elsevier BV 310 : 75-80, 2013

12 P. J. Brofman, "On the Effect of Carbon on the Stacking Fault Energy of Austenitic Stainless Steels" Springer Science and Business Media LLC 9 (9): 879-880, 1978

13 Karen Kruska, "Nanoscale characterisation of grain boundary oxidation in cold-worked stainless steels" Elsevier BV 63 : 225-233, 2012

14 J Gan, "Microstructure evolution in austenitic Fe–Cr–Ni alloys irradiated with rotons: comparison with neutron-irradiated microstructures" Elsevier BV 297 (297): 161-175, 2001

15 Yun Soo Lim, "Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment" Elsevier BV 108 : 125-133, 2016

16 R. Pathania, "Fontevraud 7" 26-, 2010

17 D.J Edwards, "Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 °C" Elsevier BV 317 (317): 13-31, 2003

18 G.S Was, "Emulation of neutron irradiation effects with protons: validation of principle" Elsevier BV 300 (300): 198-216, 2002

19 Ji-Jung Kai, "Effects of proton irradiation on the microstructural and microchemical evolution of Inconel 600 alloy" Elsevier BV 207 : 286-294, 1993

20 Lin Shao, "Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions" Elsevier BV 453 (453): 176-181, 2014

21 Dongyue Chen, "Depth distribution of Frank loop defects formed in ion-irradiated stainless steel and its dependence on Si addition" Elsevier BV 365 : 503-508, 2015

22 Z. Jiao, "Deformation microstructure of proton-irradiated stainless steels" Elsevier BV 361 (361): 218-227, 2007

23 S. J. Zinkle, "Comprehensive Nuclear Materials, Vol. 1" Elsevier 2012

24 Kale J. Stephenson, "Comparison of the microstructure, deformation and crack initiation behavior of austenitic stainless steel irradiated in-reactor or with protons" Elsevier BV 456 : 85-98, 2015

25 R. C. Newman, "Another Way to Think About the Critical Oxide Volume Fraction for the Internal-to-External Oxidation Transition?" 64 : 721-, 2008

26 T. Fujii, "Analysis of the early stage of stress corrosion cracking in austenitic stainless steel by EBSD and XRD" 172 : 110882-, 2021

27 Zheng-cao Li, "Analysis of Defects Formation and Mobility during Ion Irradiation by Coherent Precipitates" Japan Institute of Metals 47 (47): 259-262, 2006

28 O.K. Chopra, "A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels" Elsevier BV 409 (409): 235-256, 2011

29 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" Elsevier BV 114 : 15-24, 2016

30 Peter L. Andresen, "A historical perspective on understanding IASCC" Elsevier BV 517 : 380-392, 2019