DOI QR코드

DOI QR Code

New Engineering Methods for Non-Linear Deflection Estimation of Cylinder under Bending

굽힘 모멘트가 작용하는 실린더의 비선형 처짐량 예측을 위한 새로운 공학적 계산식

  • 허남수 (성균관대학교 기계공학부) ;
  • 김윤재 (고려대학교 기계공학과) ;
  • 김영진 (성균관대학교 기계공학부) ;
  • 정현규 (한국원자력연구소 원자력로봇랩) ;
  • 이동훈 (한국원자력연구소 원자력로봇랩)
  • Published : 2004.03.01

Abstract

This paper proposes engineering estimation equations for the maximum deflection of a cylinder subject to bending under elastic-plastic and elastic-creep conditions. Being based on the reference stress approach, the proposed equations are simple to use and can accommodate general tensile and creep behaviours. Validation against detailed 3-D FE results using actual stress-strain data and realistic creep-deformation data shows excellent agreement, which provides confidence in the use of the proposed equation. Based on the proposed equations, together with information on in-service inspection data, discussion is given how to estimate future time-dependent and time-independent deflection of the CANDU pressure tube. Thus the present result would be valuable information for integrity assessment of the CANDU pressure tube.

Keywords

References

  1. Kim,Y.J., Kwak, S.L., Lee, J.S. and Park, Y.W., 2003, 'Integrity Evaluation System of CANDU Reactor Pressure Tube,' KSME International Journal, vol. 17, No. 7, pp. 947-957.
  2. Domizzi, G, Enrique, R.A., Ovejero-Garcia, J. and Buscaglia, G.C., 1996, 'Blister Growth in Zirconium Alloys:Experimentation and Modeling,' Journal of Nuclear Materials, Vol. 229, pp. 36-47. https://doi.org/10.1016/0022-3115(95)00204-9
  3. CSA, 1994, 'Periodic Inspection of CANDU Nuclear Power Plant Components,' CAN/CSA-N285.4.
  4. Penny, R.K. and Marriot, D.L., 1995, 'Design for Creep $2^nd$ Edition, Chapman & Hall, London, UK, pp. 111-121.
  5. Crandall, S.H., Dahl, N.C. ad Lardner,T.J., 1978, 'An Introduction to the Mechanics of Solids,' $2^nd$ Edition, McGraw-Hill, Inc., pp. 511-576.
  6. Miller, A.G, 1988, 'Review of Limit Loads of Structures Containing Defects,' International Journal of Pressure Vessels and Piping,' Vol. 32, pp. 191-327. https://doi.org/10.1016/0308-0161(88)90073-7
  7. 'ABAQUS User's manual,' Hibbit, Karlsson & Sorensen, Inc., 1999.
  8. AFCEN, 1985, 'RCC-MR:Design and Construction Rules for Mechanical Components of FBR Nuclear Islands,; Paris.
  9. Kim, Y.J., 2001, 'Contour Integral Calculations for Generalised Creep Laws within ABAQUS,' Vol. 78, No. 10, pp. 661-666. https://doi.org/10.1016/S0308-0161(01)00080-1
  10. Webster, G.A. and Ainsworth, R.A., 1994, 'High Temperature Components Life Assessment,' Chapman & Hall, London, UK, pp. 110-111.
  11. Ross-Ross, P.A. and Fidleris,V., 1973, 'Design Basis for Creep of Zirconium Alloy Components in a Fast Neutron Flux,' Paper C216/73, International Conference on Creep and Fatigue, Philadelphia, USA.