Nuclear Engineering and Technology

  • 제38권1호
  • /
  • Pages.33-44
  • /
  • 2006
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

A COMPARATIVE OVERVIEW OF THERMAL HYDRAULIC CHARACTERISTICS OF INTEGRATED PRIMARY SYSTEM NUCLEAR REACTORS

  • 발행 : 2006.02.01
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초록

This paper presents a review of small-to-medium-sized, pressurized-water-cooled nuclear power reactors whose major primary coolant systems are integrated into a reactor pressure vessel, the concepts categorized as Integrated Primary System Nuclear Reactors (IPSRs). Typical examples of these proposals of interest in this review are CAREM, SMART, IRIS and IMR, all of which are being aimed at the near term deployment. Emphasis is placed on thermal hydraulic aspects. A brief characterization of the IPSR concepts is made and comparisons of plant key parameters are shown. Discussions will follow for the core cooling under rated power conditions and natural circulation heat removal on the basis of the design data available in the public domain.

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참고문헌

  1. International Atomic Energy Agency, Status of advanced light water reactor designs, IAEA-TECDOC1391, Vienna, May (2004)
  2. International Atomic Energy Agency, Status of innovative SMR designs, IAEA-TECDOC-200X, Vienna, to be published
  3. Narabaysashi, T., et al., Development of internal CRD for next generation BWR, Proc. Int. Conf. Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), Kyoto, Japan, September, 15-19, 2003
  4. Carelli, M.D., IRIS: A global approach to nuclear power renaissance, Nuclear News, pp. 32-42, September (2003)
  5. Ishida, T., Imayoshi, S and Kanagawa, T., In-vessel Type Control Rod Drive Mechanisms for Integral-type Reactors, Proc. Int. Conf. Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), Kyoto, Japan, September, 15-19, 2003
  6. Ishida-Fukami, M.V., Development of new nuclear powered plant in Argentina, IAEA- TECDOC-1290, Vienna, (2002)
  7. Kim, H.C., et al, Safety analysis of SMART, Proc. Int. Conf. Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), Kyoto, Japan, September, 15-19, 2003
  8. Carelli, M.D., et al., The design and safety features of the IRIS reactor, Nuclear Engineering and Design, 230, pp. 151-167 (2004) https://doi.org/10.1016/j.nucengdes.2003.11.022
  9. Gotoh, M., Kanagawa, T., et al., Status of integrated modular water reactor (IMR) development, Proc. Int. Conf. Advances in Nuclear Power Plants(ICAPP'03), Cordoba, Spain, May 4-7, 2003
  10. Ishida, T., et al., Concept of passive safe small reactor for distributed energy supply system, 11th Int. Conf. Nuclear Engineering (ICONE11-36470), Tokyo, Japan, April 20-23, 2003
  11. D'Auria, F and Frogheri, M., Natural circulation limits achievable in a PWR, IAEA-TECDOC-1281, pp. 97-114 (2000)
  12. Ishii, M. and Fauske, H., Boiling and Dryout behavior in a liquid metal fast breeder reactor subassembly bundle under low heat flux and low flow conditions, Nucl Sci Eng, 84, pp 131-146 (1983) https://doi.org/10.13182/NSE83-A17719
  13. KAERI, ,SMART for Electricity Generation and Desalination, Advanced Reactor System Development, Korea Atomic Energy Research Institute (2002)