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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 저널정보
- 대한기계학회 Journal of Mechanical Science and Technology Journal of Mechanical Science and Technology Vol.20 No.3
- 발행연도
- 2006.3
- 수록면
- 319 - 328 (10page)
이용수
초록· 키워드
오류제보하기
A simple approximation method for the stress intensity factor at the tip of the axial semi-elliptical cracks on the cylindrical vessel is developed. The approximation methods, incorporated in VINTIN (Vessel INTegrity analysis-INner flaws), utilizes the influence coefficients to calculated the stress intensity factor at the crack tip. This method has been compared with other solution methods including 3-D finite element analysis for internal pressure, cooldown, and pressurized thermal shock loading conditions. For these, 3-D finite-element analyses are performed to obtain the stress intensity factors for various surface cracks with t/R=0.1. The approximation solutions are within ±2.5% of the those of finite element analysis using symmetric model of one-forth of a vessel under pressure loading, and 1-3% higher under pressurized thermal shock condition. The analysis results confirm that the approximation method provides sufficiently accurate stress intensity factor values for the axial semi-elliptical flaws on the surface of the reactor pressure vessel.
목차
Abstract
1. Introduction
2. Methods for SIF Calculation
3. Analysis Conditions and FEM Model
4. Results and Discussion
5. Conclusions
References
참고문헌 (15)
참고문헌 신청
ASME, 1995, Analysis of Flaws, ASME B&PV Code Sec. XI, App. A.
Dickson, T. L., 1994, FAVOR: A Fracture Analysis Code For Nuclear Reactor Pressure Vessels, Release 9401, ORNL/NRC/LTR/94/1.
Jang, C. H. et al., 2000, VINTIN: Vessel Integrity Analysis Inner Flaws, KEPRI Report TM. 00NP10.P2000.350.
Jang, C. H., Moonn, H. R., Jeong, I. S. and Hong, S. Y., 2001a, "Development of The Improved Probabilistic Fracture Mechanics Analysis Code: VINTIN," In 2001 KNS Spring Meeting, Cheju, Korea.
Jang, C. H., Moonn, H. R. and Jeong, I. S., 2001b, "Stress Intensity Factor Calculation For The Semi-Elliptical Surface Flaws On The Thin-Wall Cylinder Using Influence Coefficients," In 2001 KSME Spring Meeting, Cheju, Korea.
Dickson, T. L., 1994, FAVOR: A Fracture Analysis Code For Nuclear Reactor Pressure Vessels, Release 9401, ORNL/NRC/LTR/94/1.
Jang, C. H. et al., 2000, VINTIN: Vessel Integrity Analysis Inner Flaws, KEPRI Report TM. 00NP10.P2000.350.
Jang, C. H., Moonn, H. R., Jeong, I. S. and Hong, S. Y., 2001a, "Development of The Improved Probabilistic Fracture Mechanics Analysis Code: VINTIN," In 2001 KNS Spring Meeting, Cheju, Korea.
Jang, C. H., Moonn, H. R. and Jeong, I. S., 2001b, "Stress Intensity Factor Calculation For The Semi-Elliptical Surface Flaws On The Thin-Wall Cylinder Using Influence Coefficients," In 2001 KSME Spring Meeting, Cheju, Korea.
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UCI(KEPA) : I410-ECN-0101-2009-550-015347779