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소듐냉각 고속로용 증기발생기 기술분석 및 개념개발

Concept Development and Review of Current Technical Issues for SFR Steam Generator

  • 투고 : 2010.04.13
  • 심사 : 2011.07.01
  • 발행 : 2011.09.01

초록

소듐냉각 고속로를 개발함에 있어 최대 현안 중 하나가 증기발생기에서의 소듐-물 반응사고 가능성이다. 이를 개선하기 위해 지금까지 수십 종 이상 연구개발 되었지만 국가마다 그 사양이 다르고, 동일한 기종이 후속기에 다시 활용되지 못할 정도로 기술이 안정화 상태에 도달하지 못하였다. 최근 개발되고 있는 증기발생기의 공통적 목표는 소듐-물 반응사고의 조기감지 및 제어, 증기발생기의 검사 및 보수가 쉽게 용접개수를 줄이고 경제성을 높인 Benson 증기사이클을 적용하는 것이다. 이 논문에서는 지금까지 설계 또는 활용한 증기발생기들의 사양과 문제점을 비교, 분석하였고, 이를 토대로 현안 극복방안을 제시하였다.

A steam generator poses many difficulties during the development of a sodium-cooled fast reactor because of the sodium-water-reaction problems. Until now, several types of steam generators have been developed, but the specifications of these generators differed in each country. Moreover, even if a country had developed a steam generator, it was not used in the subsequent reactor because the current techniques were not stabilized to select the proper steam generator. As a common development, the Benson steam cycle with few welding locations and high economical efficiency may be adopted. Moreover, the design is dwelled on the convenience of inspection, detection, control, and maintenance for the wear caused by sodiumwater reactions. The specifications of the designed steam generators were reviewed and the current technical problems for steam generators were analyzed. Concepts were proposed to overcome the current technical problems for steam generators.

키워드

참고문헌

  1. Nam, H., Kim, J., Lee, J. and Park, C., 2011, "Review of the SFR Steam Generator," KAERI, KEARI/AR-877/2011.
  2. Nam, H., Choi, B. and Kim, J., 2010, "On the Design Concept Technology Development of a Double Wall Tube Steam Generator," Trans. Of the KSME(A), Vol. 34, No. 9, pp. 1217-1225. https://doi.org/10.3795/KSME-A.2010.34.9.1217
  3. Hishida, M., Kubo, S., Konomura, M. and Toda, M., 2007, "Progress on the Plant Design Concept of Sodium Cooled Fast Reactor," J. of Nucl. Sci. and Tech., Vol. 44, No. 3, pp. 303-308. https://doi.org/10.3327/jnst.44.303
  4. Sessions, C.E., Harman, D. and Kindell, W.H., 1974, "Nuclear Steam Generator Materials Technology: Development of Duplex Tubing for Nuclear Steam Generator," Trans. ANS, 18, pp. 117-118.
  5. Kashiwakura, J., Tachi, Y., Nagata, S., Fujii, T., Morita, T. and Fujii-e, Y., 1991, "Study of a Plant without an Intermediate System Study of the Helically Coiled Double Wall Tube Steam Generator with Fluid Head Structure," Proc. of Int. fast Reactors and Related Fuel Cycles: FR91.
  6. Kakarala, C.R. and Boardman, C.E., 1990, "Advanced Liquid Metal Reactor Helical Coil Steam Generator," ASME NE-Vol.5, Book No. G00548-1990.
  7. Kisohara, N., Moribe, T. and Sakai, T., 2006, "Flow and Temperature Distribution Evaluation on Sodium Heated Large-sized Straight Double Wall Tube Steam Generator," Proc. of ICAPP '06, Reno, USA, Jun 4-8, 516-524.
  8. IAEA, 1984, "Specialists' Meeting on Maintenance and Repair of LMFBR Steam Generators, " IWGFR/53.
  9. Riou, B., Verwaerde, D. and Mignot, G., 2009, "Design Features of Advanced Sodium Cooled Fast Reactots with Emphasis on Economics," IAEA, Int. Conf. FR09, Kyoto, Japan.
  10. Dawson, B.E., 1979, "Preliminary Design: Duplex Tube Low-Pressure Saturated steam Generator for Large LMFBR Plant,"EPRI NP-1219.
  11. ASME, 2007, "2007 ASME Boiler & Pressure Vessel Code: Section-VIII," The American Society of Mechanical Engineers.
  12. Bushman, H.W., Penney, H., Quillici, M.D. and Radtke, W.H., 1981, "Operating Experience of the EBR-II Steam Generator System," ASME 81-JPGCNE- 4.

피인용 문헌

  1. Environment vol.38, pp.12, 2014, https://doi.org/10.3795/KSME-A.2014.38.12.1415
  2. Cycle Heat Exchangers vol.38, pp.12, 2014, https://doi.org/10.3795/KSME-A.2014.38.12.1421