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Science and Technology of Nuclear Installations
Volume 2013 (2013), Article ID 290362, 18 pages
http://dx.doi.org/10.1155/2013/290362
Review Article

Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea

Korean Atomic Energy Research Institute (KAERI), 989-111 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea

Received 28 September 2012; Revised 16 February 2013; Accepted 26 February 2013

Academic Editor: Wei Shen

Copyright © 2013 Yeong-il Kim et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. “The 5th basic plan for long term,” Electricity Supply and Demand (2010–2024) 2010-490, Ministry of Knowledge Economy, 2010.
  2. D. H. Hahn, “Status of the fast reactor technology development program in Korea,” in Proceedings of the 40th Technical Working Group on Fast Reactors Meeting (TWG-FR '07), Tsuruga, Japan, May 2007.
  3. D. Hahn et al., “KALIMER-600 conceptual design report,” KAERI/TR-3381/2007, Korea Atomic Energy Research Institute, Daejeon, Korea, 2007. View at Google Scholar
  4. H. Song, S. J. Kim, H. Y. Jeong, and Y. I. Kim, “Design studies on a large-scale sodium-cooled tru burner,” in Proceedings of the International Conference on Advances in Nuclear Power Plants (ICAPP '08), pp. 450–457, June 2008. View at Scopus
  5. IAEA, Fast Reactor Database 2006 Update, IAEA-TECDOC-1531, 2006.
  6. D. E. Kim, M. H. Kim, J. E. Cha, and S. O. Kim, “Numerical investigation on thermal-hydraulic performance of new printed circuit heat exchanger model,” Nuclear Engineering and Design, vol. 238, no. 12, pp. 3269–3276, 2008. View at Publisher · View at Google Scholar · View at Scopus
  7. J. E. Cha et al., “Report on the design concepts of Na/CO2 heat exchangers,” Gen IV International Forum Report SFR/CDBOP/2011/015, 2011. View at Google Scholar
  8. J.-H. Eoh, H. C. No, Y. H. Yoo, and S. O. Kim, “Sodium-CO2 interaction in a supercritical CO2 power conversion system coupled with a sodium fast reactor,” Nuclear Technology, vol. 173, no. 2, pp. 99–114, 2011. View at Google Scholar · View at Scopus
  9. J. H. Eoh, H. C. No, Y. H. Yoo, J. Y. Jeong, J. M. Kim, and S. O. Kim, “Wastage and self-plugging by a potential CO2 ingress in a supercritical CO2 power conversion system of an SFR,” Journal of Nuclear Science and Technology, vol. 47, no. 11, pp. 1023–1036, 2010. View at Publisher · View at Google Scholar · View at Scopus
  10. Y. I. Chang, “Technical rationale for metal fuel in fast reactor,” Nuclear Engineering and Technology, vol. 39, no. 3, 2007. View at Google Scholar
  11. C. L. Trybus, “Injection casting of U-Zr-Mn, surrogate alloy for U-Pu-Zr-Am-Np,” Journal of Nuclear Materials, vol. 224, p. 305, 1995. View at Google Scholar
  12. C. T. Lee et al., “Casting technology development for SFR metallic fuel,” in Proceedings of Global-2009, Paris, France, September 2009.
  13. R. E. Macfarlane, “TRANSX 2: a code for interfacing MATXS cross-section libraries to nuclear transport codes,” LA-12312-MS, 1992.
  14. R. E. Alcouffe et al., “DANTSYS: a diffusion accelerated neutral particle transport code system,” LA-12969-M, 1995.
  15. B. J. Toppel, “A user's guide for the REBUS-3 fuel cycle analysis capability,” ANL-83-2, 1983.