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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.8
- 수록면
- 210 - 229 (20page)
- DOI
- 10.14773/cst.2021.20.4.210
이용수
초록· 키워드
오류제보하기
To safely operate domestic nuclear power plants approaching the end of their design life, the material degradationvmanagement strategy of the components is important. Among studies conducted to improve the soundness of nuclear reactor components, research methods for understanding the degradation of reactor internals and preparing management strategies were surveyed. Since the IGSCC (Intergranular Stress Corrosion Cracking) initiation and propagation process is associated with metal dissolution at the crack tip, crack initiation sensitivity was decreased in the hydrogenated water with decreased crack sensitivity but occurrence of small surface cracks increased. A stress of 50 to 55% of the yield strength of the irradiated materials was required to cause IASCC (Irradiation Assisted Stress Corrosion Cracking) failure at the end of the reactor operating life. In the threshold-stress analysis, IASCC cracks were not expected to occur until the end of life at a stress of less than 62% of the investigated yield strength, and the IASCC critical dose was determined to be 4 dpa (Displacement Per Atom). The stainless steel surface oxide was composed of an internal Cr-rich spinel oxide and an external Fe and Ni-rich oxide, regardless of the dose and applied strain level.
목차
등록된 정보가 없습니다.
참고문헌 (14)
참고문헌 신청
임연수 / 2021 / 양성자 조사가 316 스테인리스강의 미세조직과 표면산화 특성에 미치는 영향 / CORROSION SCIENCE AND TECHNOLOGY 20(3):158~168
D. Féron / 2012 / Behavior of stainless steels in pressurized water reactor primary circuits / Journal of Nuclear Materials 427(1-3):364~377
Gen Furutani / 2001 / Stress corrosion cracking on irradiated 316 stainless steel / Journal of Nuclear Materials 288(2-3):179~186
W. E. Ruther / 1988 / Effect of Temperature and Ionic Impurities at Very Low Concentrations on Stress Corrosion Cracking of AISI 304 Stainless Steel / CORROSION 44(11):791~799
S. Zhang / 1998 / Inhibition Effect of the Borate Ion on Intergranular Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel / CORROSION 54(6):428~434
D. Féron / 2012 / Behavior of stainless steels in pressurized water reactor primary circuits / Journal of Nuclear Materials 427(1-3):364~377
Gen Furutani / 2001 / Stress corrosion cracking on irradiated 316 stainless steel / Journal of Nuclear Materials 288(2-3):179~186
W. E. Ruther / 1988 / Effect of Temperature and Ionic Impurities at Very Low Concentrations on Stress Corrosion Cracking of AISI 304 Stainless Steel / CORROSION 44(11):791~799
S. Zhang / 1998 / Inhibition Effect of the Borate Ion on Intergranular Stress Corrosion Cracking of Sensitized Type 304 Stainless Steel / CORROSION 54(6):428~434
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