[논문]양성자 조사가 316 스테인리스강의 미세조직과 표면산화 특성에 미치는 영향

임연수; 김동진; 황성식; 최민재; 조성환

doi:10.14773/cst.2021.20.3.158

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 원문보기

Corrosion science and technology, v.20 no.3, 2021년, pp.158 - 168

임연수 (한국원자력연구원 재료안전기술개발부) , 김동진 (한국원자력연구원 재료안전기술개발부) , 황성식 (한국원자력연구원 재료안전기술개발부) , 최민재 (한국원자력연구원 재료안전기술개발부) , 조성환 (한국원자력연구원 재료안전기술개발부)

Abstract ▼ AI-Helper

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.

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표/그림 (12)

표 Table 1. Chemical composition of 316 stainless steel (wt%)
그림 Fig. 1. Predicted displacements per atom (dpa) depending on the irradiation depth for protons accelerated with an energy of 2 MeV, by the Kinchin-Pease (or, quick calculation) model with a displacement energy of 40 eV in the SRIM code
그림 Fig. 2. (a) OM and (b) SEM images showing the microstructural features of 316 stainless steel before proton irradiation
그림 Fig. 3. TEM bright field images and related SADP showing (a) dislocation and (b) stacking fault morphologies taken from 316 stainless steel before proton irradiation
그림 Fig. 4. Dislocation morphologies in the proton-irradiated 316 stainless steel with radiation doses of (a) ~ 1 dpa and (b) ~ 4 dpa
그림 Fig. 5. Behavior of micro-void formation in the proton-irradiated 316 stainless steel with radiation doses of (a) ~ 8 dpa and (b) ~ 12 dpa
그림 Fig. 6. OM image showing the oxidation surfaces of the non-irradiated and proton-irradiated regions of 316 stainless steel after the immersion test in a simulated PWR primary water environment at 325 °C with a test duration of 5000 hrs
그림 Fig. 7. SEM images of the surface oxide morphologies on the (a) non-irradiated and (b) proton-irradiated regions of 316 stainless steel with a radiation dose of 4 dpa
그림 Fig. 8. STEM image of the surface oxidation layer in the non-irradiated region of 316 stainless steel, and EDS compositional maps of O, Cr, Ni and Fe
그림 Fig. 9. (a) STEM image of the surface oxidation layer in the non-irradiated region of 316 stainless steel, and (b) compositional variations of Cr, Fe and Ni obtained from a line profiling across a grain boundary denoted by EDS1 in (a)
그림 Fig. 10. STEM image of the surface oxidation layer in the proton-irradiated region of 316 stainless steel with a radiation dose of 4 dpa, and EDS compositional maps of O, Cr, Ni and Fe
그림 Fig. 11. (a) STEM image of the surface oxidation layer in the proton-irradiated region of 316 stainless steel with a radiation dose of 4 dpa, and (b) compositional variations of Cr, Fe and Ni obtained from a line profiling across a grain boundary denoted by EDS2 in (a)

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