대한기계학회논문집A (Transactions of the Korean Society of Mechanical Engineers A)

  • 제25권10호
  • /
  • Pages.1567-1574
  • /
  • 2001
  • /
  • 1226-4873(pISSN)
  • /
  • 2288-5226(eISSN)
대한기계학회 (The Korean Society of Mechanical Engineers)
권호 표지
DOI QR코드

DOI QR Code

유한요소해석을 이용한 원자로용기 압력-온도 한계곡선의 평가

Evaluation of Pressure-Temperature Limit Curve for the Safe Operation of an RFV based on 3-D Finite Element Analyses

  • 이택진 (한국원자력안전기술원 방사선. 공학연구실) ;
  • 박윤원 (한국원자력안전기술원 방사선. 공학연구실) ;
  • 이진호 (한국원자력안전기술원 방사선. 공학연구실) ;
  • 최재붕 (성균관대학교 기계공학부) ;
  • 김영진
  • 발행 : 2001.10.01
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

In order to operate an RPV safely it is necessary to keep the pressure-temperature (P-T) limit during the heatup and cooldown process. While the ASME Code provides the P-T limit curve for safe operation, this limit curve has been prepared under conservative assumptions In this paper the effects of conservative assumptions involved in the P-T limit curve specified in the ASME Code Sec. XI were investigated. Three different parameters the crack depth the cladding thickness and the cooling rate, were reviewed based on 3-D finite element analyses. Also the constraint effect on P-T limit curve generation was investigated based on J- T approach. It was shown that the crack depth and the constraint effect change the safe region in P-T limit curve significantly Therefore it is recommended to prepare a more precise P-T limit curve based on finite element analysis to obtain P-T limit for safe operation of an RPV.

키워드

참고문헌

  1. 이택진, 최재붕, 김영진, 박윤원, 정명조, 2000, '원자로용기 건전성 평가를 위한 RVIES 시스템의 개발,' 대한기계학회논문집(A), 제 24 권 제 8 호,pp. 2083-2090
  2. ASME Boiler and Pressure Vessel Code Sec. XI, 1998, 'Fracture Toughness Criteria for Protection Against Failure,' Appendix G
  3. PVRC Ad Hoc Group on Toughness Requrements, 1972, 'PVRC Recommendations on Toughness Requirements for Ferritic Materials,' WRC BULLETIN 175
  4. ASME Boiler and Pressure Vessel Code Sec. Ⅲ, 1989, 'Protection Against Nonductile Failure,' Appendix G
  5. Dickson, T. L., McAfee, W. J., Pennell, W. E., and Williams, P. T., 1999, 'Evaluation of Margins in the ASME Rules for Defining the P-T Curve for a RPV,' Proceedings of ASME Pressure Vessel and Pipings, PVP-Vol. 385
  6. Nanstadt, R. K., Keeney, J. A., and McCabe, D. E., 1993, 'Preliminary Review of the Bases for the KIC Curve in the ASME Code,' ORNL/NRC/LTR/93-15
  7. Theiss, T. J., Shum, D. K., and Rolfe, S. T., 1992 'Experimental and Analytical Investigation of the Shallow-Flaw Effect in Reactor Pressure Vessels,' NUREG/CR-5886(ORNL/TM-12115)
  8. Marshall, W., 1982, 'An Assessment of the Integrity of PWR Pressure Vessels,' .Second Report by a Study Group under the chairmanship of Dr. W. Marshall, UKAEA
  9. Dickson, T. L., Bass, B. R., Williams, P. T., 2000, 'Validation of a Linear-Elastic Fracture Methodology for Postulated Flaws Embedded in the Wall of a Nuclear Reactor Pressure Vessel,' Proceedings of ASME Pressure Vessel and Pipings, PVP-Vol.403
  10. Bhandari, S., McGarry, D., McAllister, S., 1998, 'Designing for Crack Growth in NESC-1 Spinning Cylinder,' '98 ASME, PVP-Vol.362, pp.243-247
  11. Keeney, J. A., Bass, B. R., Williams, P. T., Pugh, C. E., 1998, 'Pretest Fracture Evaluation of The NESC-1 Spinning-Cylinder Experiment,' '98 ASME, PVP-Vo.362,pp.253-260
  12. Moinereau, D., Faidy, C., Bhadari, S., Guichard, D., Valeta, M. P., Courtois, M., 1998, 'NESC Spinning Cylinder Thermal Shock Experiment French Contribution to the Pre Test Fracture Analysis Evaluation,' '98 ASME,PVP-Vol.362,pp.261-279
  13. Hutchinson,J.W., 1968, 'Singular Behavior at the End of a Tensile Crack in a Hardening Material,' Journal of the Mechanics and Physics of Solids, Vol.16,pp.16-31 https://doi.org/10.1016/0022-5096(68)90014-8
  14. 서헌, 한태수, 이형일, 1999, '구속상태를 고려한 반타원 표면균열의 파손평가선도,' 대한기계학회논문집(A), 제 23 권 제 11 호,pp. 2022-2032
  15. Rice, J. R. and Rosengren, G. H., 1968, 'Plane Strain Deformation Near a Crack Tip in a Power-Law Hardening Material,' Journal of the Mechanics and Physics of Solids, Vol. 16, pp. 1-12 https://doi.org/10.1016/0022-5096(68)90013-6
  16. Shih, C. F., 1983, 'Tables of Hutchinson-Rice-Rosengren Singular Field Quantities,' Brown University, Province, RI
  17. Betegon, C., Hancock, J. W., 1991, 'Two-Parameter Characterization of Elastic-Plastic Crack-Tip-Fields,' Journal of Applied Mechanics, Vol. 58, pp. 104-110
  18. O'Dowd, N. P., Shih, C. F., 1991, 'Family of Crack Tip Fields Characterized by A Triaxiality Parameter - I Structure of Fields,' Journal of Mechanics and Physics of Solids, Vol. 39, No. 8, pp. 989-1015 https://doi.org/10.1016/0022-5096(91)90049-T
  19. Leevers, P. S., Radon, J. C., 1982, 'Inherent Stress Biaxiality in Various Fracture Specimen Geometries,' International Journal of Fracture, Vol. 19,pp.311-325 https://doi.org/10.1007/BF00012486
  20. O'Dowd, N. P., Shih, C. F., 1992, 'Family of Crack-Tip Fields Characterized by a Triaxiality Parameter - Ⅱ. Frcture Applications,' Journal of the Mechanics and Physics of Solids, Vol. 40, No. 5, pp. 939-963 https://doi.org/10.1016/0022-5096(92)90057-9
  21. ASME Boiler and Pressure Vessel Code Sec. Ⅱ, 1995, 'Materials,' Part D
  22. USNRC, 1998, 'Radiation Embrittlement of Reactor Vessel Materials,' Regulatory Guide 1.99, Rev.2,