Development of a Web-based Fatigue Life Evaluation System for Primary Components in a Nuclear Power Plant

원자력발전소 1차 계통 주요기기에 대한 웹기반 피로수명평가 시스템 개발

  • 서형원 (성균관대학교 기계공학부) ;
  • 이상민 (성균관대학교 기계공학) ;
  • 최재붕 (성균관대학교 기계공학) ;
  • 최성남 (한국전력공사 전력연구) ;
  • 장기상 (한국전력공사 전력연구) ;
  • 홍승렬 (한국전력공사 전력연구) ;
  • 김영진 (성균관대학교 기계공학부)
  • Published : 2004.06.01


A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including regular in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage the integrity issues on a nuclear power plant. In this paper, a web-based fatigue life evaluation system for primary components in nuclear power plant is proposed. This system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant.


Nuclear Power Plant;Facture Mechanics Analysis;Fatigue Life Evaluation;Web-Based


  1. Cloud, R. L. and Palusamy, S. S., 1982, 'A Summary and Critical Evaluation of Stress Intensity Factor Solutions of Corner Cracks at the Edge of a Hole,' Welding Research Council Bulletin 276
  2. Horton, I., 2002, Beginning JAVA 2 SDK 1.4 edition, Wiley Publishing Inc.
  3. Raju, I. S. and Newman, J. C., 1982, 'Stress Intensity Factors for Internal and External Surface Cracks in Cylindrical Vessels,' Journal of Pressure Vessel Technology, Vol. 104, pp. 293-298
  4. Shah, R. C. and Kobayashi, A. S., 1971, 'Stress Intensity Factor for An Elliptical Crack Under Arbitrary Normal Loading,' Engineering Fracture Mechanics, Vol. 3, pp. 71-96
  5. Bachalet, C. and Bamford, W. H., 1976, 'Stress Intensity Factors for Continuous Surface Flaws in Reactor Pressure Vessles in Mechanics of Crack Growth,' ASTM STP 590, pp. 385-402
  6. Sih, G. C., 1973, Handbook of Stress Intensity Factor, Lehigh University, Bethlehem, pp. 3.3.1-4
  7. Codd, E. F., 1970, 'A Relational Model of Data for Large Shared Data Bank,' Communications of the ACM, Vol. 12, No. 6, pp. 377-387
  8. Gallardo, D. J., 2001, Java Oracle Database Development, Prentice Hall PTR, New Jersey
  9. Bloom, R. B., 2002, Apache Server 2.0: The Complete Reference, Osborne McGraw-Hill, Europe
  10. Falkman, D., 2001, Jrun Web Application Construction Kit, Macmillan Computer Pub, England
  11. Park, S. M., 2002, JAVA2 programming for developer, SAMSUNG SDS e-Campus, Seoul
  12. Lee, S. H., 1997, Development of Integrity Evaluation System for Reactor Pressure Vessel, Master's Thesis, Sungkyunkwan University, Suwon
  13. Kim, J. S., 1998, Development of the Integrity Evaluation System for Primary Nuclear Power Plant Components, Master's Thesis, Sungkyunkwan University, Suwon
  14. ASME, 1998, Rules for In-Service Inspection of Nuclear Power Plant Components, ASME Boiler and Pressure Vessel Code, Section XI
  15. Paris, P. C. and Etdogan, F., 1963, 'A Critical Analysis of Crack Propagation Laws,' Journal of Basic Engineering, Vol. 85, pp. 528-534
  16. Jhung, M. J, 1996, 'Development of Structural Integrity Evaluation Program for Reactor Vessel Under Pressurized Thermal Shock,' Trans. of COSEIK, Vol. 9, No. 2, pp. 153-161
  17. Welding Research Council Bulletin 276 A Summary and Critical Evaluation of Stress Intenstiy Factor Solutions of Corner Cracks at the Edge of a Hol Cloud,R.L.;Palusamy,S.S.