Dynamic Characteristics of the Integral Reactor SMART

  • Published : 2001.02.01

Abstract

In this study, a dynamic analysis of the integral reactor SMART (System-integrated Modular Advanced ReacTor) under postulated seismic events is performed to review the response characteristics of the major components. To enhance the feasibility of an analysis model, a detailed finite element model is synchronized with the products of concurrent design activities. The artificial time history, which has been applied to the seismic analysis for the Korean Standard Nuclear Power Plant (KSNP), is chosen to envelop broad site specifics in Korea. Responses in the horizontal direction are found slightly amplified, while those in the vertical direction are suppressed. Since amplified response is monitored at the control element drive mechanism (CEDM), minor design provision is considered to enhance the integrity of the subsystem.

Keywords

References

  1. Y.W. Kim, et al., 'Review of Design Characteristics of the Integral PWR as Advanced Reactor,' Journal of the Korea Nuclear Society, pp.269-279, Vol. 27, No.2 (1995)
  2. J.H. Kim, et al., 'Preliminary Design Concept of Primary Components of the Advanced Integral Reactor,' Proc. of 1995 Spring Conference of the Korea Nuclear Society, pp. 741-746 (1995)
  3. J.K. Seo, et al., 'Advanced Integral Reactor (SMARY) for Nuclear Desalination,' Proc. of the Symposium on Desalination of Seawater with Nuclear Energy, IAEA-SM-347/40, Daejon, May (1997)
  4. K.B. Park, 'Reactor Vessel Assembly of the Integral Reactor SMART,' Journal of the KSME, Vol. 39, No. 4 (1999)
  5. Y.W. Kim, et al., 'Design Concept of the Steam Generator for an Advanced Integral Reactor,' Proc. of 1995 Spring Conference of the Korea Nuclear Society, pp. 735-740 (1995)
  6. T.W. Kim, et al., 'A Study of the Thermal Movement of the Reactor Coolant System for PWR,' Journal of the Korea Nuclear Society, pp. 393-402, Vol. 27, No. 3 (1995)
  7. T.W. Kim, et al., 'Integrity of the Reactor Vessel Support System for a Postulated Reactor Vessel Closure Head Drop Event,' Journal of the Korea Nuclear Society, pp. 576-582, Vol. 28, No. 6 (1996)
  8. T.W. Kim, et al., 'Dynamic Characteristics of the SMART Reactor Vessel Assembly,' Trans. of the 15th intl. Conf. on SMIRT, Vol. VII, pp.233-240, Seoul, Korea (1999)
  9. SDRC, 'Course Guide Advanced Analysis,' (1997)
  10. HKS, 'ABAQUS User's Manual' (1998)
  11. United State Nuclear Regulatory Commission, 'Design Response Spectra for Seismic Design of Nuclear Power Plants,' US NRC Reg. Guide, 1.60 (1973)
  12. United State Nuclear Regulatory Commission, 'Seismic Design Parameters', US NRC Standard Review Plan, 3.7.1 (1981)