DOI QR코드

DOI QR Code

Statistical analysis of parameter estimation of a probabilistic crack initiation model for Alloy 182 weld considering right-censored data and the covariate effect

  • Park, Jae Phil (School of Mechanical Engineering, Pusan National University) ;
  • Park, Chanseok (Department of Industrial Engineering, Pusan National University) ;
  • Oh, Young-Jin (Korea Electric Power Corporation (KEPCO) Engineering and Construction, Co, Ltd) ;
  • Kim, Ji Hyun (Department of Nuclear Engineering, School of Mechanical and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ;
  • Bahn, Chi Bum (School of Mechanical Engineering, Pusan National University)
  • Received : 2017.06.05
  • Accepted : 2017.09.20
  • Published : 2018.02.25

Abstract

To ensure the structural integrity of nuclear power plants, it is essential to predict the lifetime of Alloy 182 weld, which is used for welding in nuclear reactors. The lifetime of Alloy 182 weld is directly related to the crack initiation time. Owing to the large time scatter in most crack initiation tests, a probabilistic model, such as the Weibull distribution, has mainly been adopted for prediction. However, since statistically more advanced methods than current typical methods may be applied, we suggest a statistical procedure for parameter estimation of the crack initiation time of Alloy 182 weld, considering right-censored data and the covariate effect. Furthermore, we suggest a procedure for uncertainty evaluation of the estimators based on the bootstrap method. The suggested statistical procedure can be applied not only to Alloy 182 weld but also to any material degradation data set including right-censored data with covariate effect.

Keywords

References

  1. W. Lunceford, T. DeWees, P. Scott, EPRI Materials Degradation Matrix, EPRI, Palo Alto, CA, 2013. Rev. 3, Report No. 3002000268.
  2. P. Scott, M.-C. Meunier, Materials Reliability Program: Review of Stress Corrosion Cracking of Alloys 182 and 82 in PWR Primary Water Service (MRP- 220), EPRI, Palo Alto, CA, 2007. Report No. 1015427.
  3. K.J. Kim, E.S. Do, Inspection of Bottom Mounted Instrumentation Nozzle, Korea Institute of Nuclear Safety (KINS), Daejeon, 2015 (in Korean), Report No. KINS/ RR-1360.
  4. G. Troyer, S. Fyfitch, K. Schmitt, G. White, C. Harrington, Dissimilar metal weld PWSCC initiation model refinement for xLPR part I: a survey of alloy 82/182/ 132 crack initiation literature, in: 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Ottawa, 2015.
  5. M. Erickson, F. Ammirato, B. Brust, D. Dedhia, E. Focht, M. Kirk, C. Lange, R. Olsen, P. Scott, D. Shim, G. Stevens, G. White, Models and Inputs Selected for Use in the xLPR Pilot Study, EPRI, Palo Alto, CA, 2011. Report No. 1022528.
  6. U. Genschel, W.Q. Meeker, A comparison of maximum likelihood and medianrank regression for Weibull estimation, Qual. Eng. 22 (2010) 236-255. https://doi.org/10.1080/08982112.2010.503447
  7. J.P. Park, C.B. Bahn, Uncertainty evaluation of Weibull estimators through Monte Carlo simulation: applications for crack initiation testing, Materials 9 (2016) 521. https://doi.org/10.3390/ma9070521
  8. J.P. Park, C. Park, J. Cho, C.B. Bahn, Effects of cracking test conditions on estimation uncertainty for Weibull parameters considering time-dependent censoring interval, Materials 10 (2017) 3.
  9. M.R. Chernick, Bootstrap Methods: A Guide for Practitioners and Researchers, second ed., Wiley, 2007.
  10. GetData Graph Digitizer Ver. 2.26.0.20, http://getdata-graph-digitizer.com/.
  11. R.A. Fisher, L.H.C. Tippett, Limiting forms of the frequency distribution of the largest or smallest member of a sample, Math. Proc. Camb. Philos. Soc. (1928) 180-190.
  12. J. McCool, Using the Weibull Distribution: Reliability, Modeling, and Inference, John Wiley & Sons, Hoboken, 2012.
  13. P. Scott, R. Kurth, A. Cox, R. Olson, D. Rudland, Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, Swedish Radiation Safety Authority, 2010. MERIT Final Report.
  14. W. Shack, O. Chopra, Statistical initiation and crack growth models for stress corrosion cracking, in: ASME 2007 Pressure Vessels and Piping Conference, 2007, pp. 337-344.
  15. M. Mills, Introducing Survival and Event History Analysis, Sage Publications, 2011.
  16. ReliaSoftCorporation, Life Data Analysis Reference Book (e-book), http://www.ReliaSoft.com.
  17. J.D. Hong, C. Jang, T.S. Kim, PFM application for the PWSCC integrity of Ni-base alloy welds e development and application of PINEP-PWSCC, Nuclear Engineering and Technology 44 (2012) 961-970. https://doi.org/10.5516/NET.07.2012.017
  18. R. Staehle, Bases for Predicting the Earliest Penetrations Due to SCC for Alloy 600 on the Secondary Side of PWR Steam Generators, USNRC, 2001. Report No. NUREG/CR-6737.
  19. E.L. Kaplan, P. Meier, Nonparametric estimation from incomplete observations, J. Am. Statis. Assoc. 53 (1958) 457-481. https://doi.org/10.1080/01621459.1958.10501452
  20. B. Efron, Censored data and the bootstrap, J. Am. Statis. Assoc. 76 (1981) 312-319. https://doi.org/10.1080/01621459.1981.10477650
  21. K. Schmitt, G. White, G. Troyer, S. Fyfitch, C. Harrington, Dissimilar metal weld PWSCC initiation model refinement for xLPR part II: a statistical framework for the integration of field and laboratory data, in: 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Ottawa, 2015.

Cited by

  1. Weibull and Bootstrap-Based Data-Analytics Framework for Fatigue Life Prognosis of the Pressurized Water Nuclear Reactor Component Under Harsh Reactor Coolant Environment vol.3, pp.1, 2018, https://doi.org/10.1115/1.4045162
  2. Development of probabilistic primary water stress corrosion cracking initiation model for alloy 182 welds considering thermal aging and cold work effects vol.53, pp.6, 2018, https://doi.org/10.1016/j.net.2020.12.005