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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.1
- 수록면
- 158 - 168 (11page)
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초록· 키워드
오류제보하기
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.
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참고문헌 (30)
참고문헌 신청
J. McKinley / 2013 / Proc. of the 16th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor
R. Pathania / 2010 / Fontevraud 7 :26
S.M Bruemmer / 1999 / Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals / Journal of Nuclear Materials 274(3):299~314
O.K. Chopra / 2011 / 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):235~256
Peter L. Andresen / 2019 / A historical perspective on understanding IASCC / Journal of Nuclear Materials 517:380~392
R. Pathania / 2010 / Fontevraud 7 :26
S.M Bruemmer / 1999 / Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals / Journal of Nuclear Materials 274(3):299~314
O.K. Chopra / 2011 / 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):235~256
Peter L. Andresen / 2019 / A historical perspective on understanding IASCC / Journal of Nuclear Materials 517:380~392
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