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Quantitative Estimation of Radiation Damage in Reactor Pressure Vessel Steels by Using Multiscale Modeling

멀티스케일 모델링을 이용한 압력용기강의 조사손상 정량예측

  • 이경근 (한국원자력연구원) ;
  • 권준현 (한국원자력연구원, 원자력재료안전연구부)
  • Received : 2014.06.11
  • Accepted : 2014.06.26
  • Published : 2014.07.01

Abstract

In this work, an integrated model including molecular dynamics and chemical rate theory was implemented to calculate the growth of point defect clusters(PDC) and copper-rich precipitates(CRP) which could change the mechanical properties of reactor pressure vessel(RPV) steels in a nuclear power plant. A number of time-dependent differential equations were established and numerically integrated to estimate the evolution of irradiation defects. The calculation showed that the concentration of the vacancies was higher than that of the self-interstitial atoms. The higher concentration of vacancies induced a formation of the CRPs in the later stage. The size of the CRPs was used to estimate the mechanical property changes in RPV steels, as is the same case with the PDCs. The calculation results were compared with the measured values of yield strength change and Charpy V-notch transition temperature shift, which were obtained from the surveillance test data of Korean light water reactors(LWRs). The estimated values were in fair agreement with the experimental results in spite of the uncertainty of the modeling parameters.

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