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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 1,060 - 1,068 (9page)
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초록· 키워드
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This work aims to establish a model of a primary water stress corrosion crack growth rate of Alloy 690material for the head penetration nozzles of Korean pressurized water reactors. The test material had aninhomogeneous microstructure with bands of fine-grains and intragranular carbides in the matrix ofcoarse-grains, which was similar to the archive materials of the head penetration nozzles. The crackgrowth rate was measured from the strain-hardened materials as a function of the stress intensity factorin simulated primary water at various temperatures and dissolved hydrogen contents. The effects ofstrain-hardening, temperature, and dissolved hydrogen on the crack growth rate were analyzed independently,and were then introduced as normalizing factors in the crack growth rate model. The crackgrowth rate model proposed in this work provides a key element of the tools needed to assess theprogress of a stress corrosion crack when detected in thick-wall Alloy 690 components in Koreanreactors.
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참고문헌 (20)
참고문헌 신청
황성식 / 2013 / Role of Grain Boundary Carbides in Cracking Behavior of Ni Base Alloys / Nuclear Engineering and Technology 45(1):73~80
P.M. Scott / 2007 / Corrosion Issues in Light Water Reactors - Stress Corrosion Cracking / Woodhead Publishing Ltd.
P.L. Andresen / 2009 / Unusual cold work and strain rate effects on SCC / Proc. 14th Int. Conf. On Env. Deg. Mater. Nucl. Power Syst, Water Reactors :805~845
S. M. Bruemmer / 2013 / Corrosion 69:953~963
S. W. Kim / 2015 / Corrosion 71:1071~1081
P.M. Scott / 2007 / Corrosion Issues in Light Water Reactors - Stress Corrosion Cracking / Woodhead Publishing Ltd.
P.L. Andresen / 2009 / Unusual cold work and strain rate effects on SCC / Proc. 14th Int. Conf. On Env. Deg. Mater. Nucl. Power Syst, Water Reactors :805~845
S. M. Bruemmer / 2013 / Corrosion 69:953~963
S. W. Kim / 2015 / Corrosion 71:1071~1081
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