Transactions of the Korean Society of Mechanical Engineers B (대한기계학회논문집B)

The Korean Society of Mechanical Engineers (대한기계학회)
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Analysis of Transient Performance of KALIMER-600 Reactor Pool by Changing the Elevation of Intermediate Heat Exchanger

중간 열교환기 높이 상승에 의한 KALIMER-600 원자로 풀 과도 성능 변화 분석

  • Han, Ji-Woong (Fast Reactor Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Eoh, Jae-Hyuk (Fast Reactor Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Seong-O (Fast Reactor Technology Development Division, Korea Atomic Energy Research Institute)
  • 한지웅 (한국원자력연구원 고속로기술개발부) ;
  • 어재혁 (한국원자력연구원 고속로기술개발부) ;
  • 김성오 (한국원자력연구원 고속로기술개발부)
  • Received : 2010.05.19
  • Accepted : 2010.09.27
  • Published : 2010.11.01
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Abstract

The effect of increasing the elevation of an IHX (intermediate heat exchanger) on the transient performance of the KALIMER-600 reactor pool during the early phase of a loss of normal heat sink accident was investigated. Three reactors equipped with IHXs that were elevated to different heights were designed, and the thermal-hydraulic analyses were carried out for the steady and transient state by using the COMMIX-1AR/P code. In order to analyze the effects of the elevation of an IHX between reactors, various thermal-hydraulic properties such as mass flow rate, core peak temperature, RmfQ (ratio of mass flow over Q) and initiation time of decay heat removal via DHX (decay heat exchanger) were evaluated. It was found that with an increase in the IHX elevation, the circulation flow rate increases and a steep rise in the core peak temperature under the same coastdown flow condition is prevented without a delay in the initiation of the second stage of cooling. The available coastdown flow range in the reactor could be increased by increasing the elevation of the IHX.

소듐냉각 고속로 내부기기 배치 변경에 의한 초기냉각 성능변화를 검토하기 위하여 중간열교환기의 수직배치가 다른 3개의 원자로를 대상으로 COMMIX-1AR/P 코드를 활용한 다차원 해석을 수행하였다. 원통좌표계의 중심축을 기준으로 원주방향의 1/4 부분만을 모델링하고 정상상태 및 과도상태 분석을 수행하여 IHX 수직배치 변화가 초기 냉각 특성에 미치는 영향을 분석하였고, DHX를 통한 후기 냉각 모드 개시 시점에 미치는 영향도 분석하였다. 분석 결과 IHX 수직배치 상승은 원자로 풀내부 자연 순환 유량을 증가시켜 초기 냉각과정에서 노심 최고 온도의 급격한 상승을 방지할 수 있으며, 초기냉각 성능을 향상시키기 위한 관성회전차의 가용설계재원의 범위도 확대시킨다. 또한 IHX 수직배치 상승은 후기냉각모드에 큰 영향을 주지 않으면서 초기냉각성능의 향상에 기여할 수 있을 것으로 사료된다.

Keywords

References

  1. Till, C. E., Chang, Y. I. and Hannum, W. H., 1997, "The Integral Fast Reactor-An Overview," Progress in Nuclear Energy, Vol. 31, No. 1/2, pp.3-11. https://doi.org/10.1016/0149-1970(96)00001-7
  2. "A Technology Roadmap for Generation IV Nuclear Energy Systems," U.S. DOE Nuclear Energy Research Advisory Committee and the Generation IV International Forum, GIF-002-00.
  3. Hahn, D. H. et al., 2007, "KALIMER-600 Conceptual Design Report," KAERI/TR-3381/2007.
  4. Han, J. W., Eoh, J. H., Lee, T. H. and Kim, S. O., 2009, "Transient Performance Analysis of the Reactor Pool in KALIMER-600 with an Inertia Moment of a Pump Flywheel," Transactions of Korean Society of Mechanical Engineers B, Vol. 33, No. 6, pp.418-426. https://doi.org/10.3795/KSME-B.2009.33.6.418
  5. Han, J. W., Lee, T. H., Eoh, J. H. and Kim, S. O., 2009, "Investigation into the effects of a Coastdown Flow on the Characteristics of Early Stage Cooling of the Reactor Pool in KALIMER-600," Annals of Nuclear Energy, Vol. 36, No. 9, pp.1325-1332. https://doi.org/10.1016/j.anucene.2009.07.004
  6. Sim, Y. S., 2008, "Introduction of IDINHX, A New Heat Exchanger for Passive Decay Heat Removal," Nuclear Technology, Vol. 161, MAR. pp.299-314. https://doi.org/10.13182/NT08-A3928
  7. Kim, S. O., Eoh, J. H. and Choi, H. K., 2002, "Analysis of Free Surface Motions in the Hot Pool of KALIMER," Korean Society of Computational Fluid Engineering, Vol. 7, No. 3, Sep., pp.44-52.
  8. Jeon, W. D., 2004, "Flow Analysis Report in KALIMER-600," KAERI, LMR/FS200-AR-01/2004.
  9. Garner, P. L., Blomquist, R. N. and Gelbard, E. M., 1992, "COMMIX-1AR/P:A Three- dimensional Transient Single-phase Computer Program for Thermal Hydraulic Analysis of Single and Multicomponent Systems Volume2 : User's Guide," Argonne National Laboratory, ANL-92/33.