ASSESSMENT OF GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL $CO_2$ CYCLE

  • Published : 2006.02.01

Abstract

Various indirect power cycle options for a helium cooled gas cooled fast reactor (GFR) with particular focus on a supercritical $CO_2(SCO_2)$ indirect cycle are investigated as an alternative to a helium cooled direct cycle GFR. The balance of plant (BOP) options include helium-nitrogen Brayton cycle, supercritical water Rankine cycle, and $SCO_2$ recompression Brayton power cycle in three versions: (1) basic design with turbine inlet temperature of $550^{\circ}C$, (2) advanced design with turbine inlet temperature of $650^{\circ}C$ and (3) advanced design with the same turbine inlet temperature and reduced compressor inlet temperature. The indirect $SCO_2$ recompression cycle is found attractive since in addition to easier BOP maintenance it allows significant reduction of core outlet temperature, making design of the primary system easier while achieving very attractive efficiencies comparable to or slightly lower than, the efficiency of the reference GFR direct cycle design. In addition, the indirect cycle arrangement allows significant reduction of the GFR &proximate-containment& and the BOP for the $SCO_2$ cycle is very compact. Both these factors will lead to reduced capital cost.

Keywords

References

  1. G. Sulzer, 'Verfahren zur Erzeugung von Arbeit aus Warme,' Swiss Patent CH 269599 (July 15, 1950)
  2. E. G. Feher, 'The Supercritical Thermodynamic Power Cycle', in Adv. Energy Conversion Eng., The American Soc. Of Mechanical Engineers, New York, pp.37-44 (1967)
  3. G. Angelino, 'Real Gas Effects in Carbon Dioxide Cycles', ASME 69-GT-103, American Soc. Of Mechanical Engineers (1969)
  4. R. A. STRUB and A. J. FRIEDER, 'High Pressure Indirect $CO_2$ Closed-Cycle Design Gas Turbines', Nuclear Gas Turbines, 51-61 (1970)
  5. V. Dostal, P. Hejzlar, M.J Driscoll, and N.E. Todreas, 'A Supercritical $CO_2$ Brayton Cycle for Advanced Reactor Applications,' Transactions of the American Nuclear Society, 85, (2001)
  6. V. Dostal., P. Hejzlar , M.J Driscoll., and N.E. Todreas, 'A Supercritical $CO_2$ Gas Turbine Power Cycle for Next Generation Nuclear Reactors', Proc. of ICONE-10, Arlington, Virginia, April 14 ? 18, (2002)
  7. Y. Kato, T. Niktawaki, and Y. Yoshizawa, 'A Carbon Dioxide partial Condensation Direct Cycle for Advanced Gas Cooled Fast and Thermal Reactors', Proc. of Global 2001, Paris, France, September 9-13 (2001)
  8. Y. Kato, T. Nitawaki, and Y. Muto, 'Medium Temperature Carbon Dioxide Gas Turbine Reactor', Nuclear Engineering and Design, 230, pp. 195-207, (2004) https://doi.org/10.1016/j.nucengdes.2003.12.002
  9. Y. Wang, V. Dostal, P. Hejzlar, 'Turbine Design for Supercritical $CO_2$ Brayton Cycle', Proc. of GLOBAL'03, New Orleans, November 16-20, (2003)
  10. V. Dostal., P. Hejzlar., M.J. Driscoll and Y. Wang., 'Supercritical $CO_2$ Cycle for Fast Gas-Cooled Reactor', Proc. of ASME TurboExpo: Power for Land, Sea and Air, Vienna, Austria, June 14-17, (2004)
  11. A.V. Moisseytsev, J.J. Sienicki, and D.C. Wade, 'Cycle Analysis of Supercritical Carbon Dioxide Gas Turbine Brayton Cycle Power Conversion System for Liquid Metal-Cooled Fast Reactors', Proc. of the 11th International Conference on Nuclear Engineering, ICONE-11, Tokyo, Japan, April 10-23, (2003)
  12. www.heatric.com
  13. V. Dostal., M.J Driscoll, and P. Hejzlar, 'A Supercritical Carbon Dioxide Cycle for Next Generation Nuclear Reactors', MIT-ANP-TR-100, MIT Report, March (2004)
  14. Y. Wang, G. Jr. Guenette, M.J. Driscoll and P. Hejzlar, 'Compressor Design for the Supercritical $CO_2$ Brayton Cycle', Proc. of the 2nd International Energy Conversion Engineering Conference (IECEC), paper# AIAA-2004-5722, Providence, RI, August (2004)
  15. M.P. LaBar, A.S. Shenoy, W.A. Simon and E.M. Campbell, 'Status of GT-MHR for Electricity Production', World Nuclear Association Symposium, London, UK, 3-5 September (2003)
  16. J.C. Garnier et al., 'Feasibility Study of an Advanced GFR, Design Trends and Safety Options, Status of France and U.S. Studies', Proc. of Global 2003-Atoms for Prosperity:Updating Eisenhower's Global Vision for Nuclear Energy, New Orleans, USA, November 16-20, (2003)
  17. Dewson S. J. and Grady C., HEATRICTM Workshop at MIT, Cambridge, MA, U.S.A., October 2nd, (2003)
  18. 'Modular High Temperature Gas-cooled Reactor Commercialization and Generation Cost Estimates', HTGR-90365, August (1993)
  19. Diehl H., Bodman E., 'Alloy 800 Specifications in Compliance with Component Requirements', Journal of Nuclear Materials, 171, pp. 63-70, (1990) https://doi.org/10.1016/0022-3115(90)90348-Q
  20. Haubensack D. et al, 'The COPERNIC/CYCLOP computer tool, the pre-conceptual design of generation 4 nuclear systems', NURETH11 conference, Avignon, October 2005
  21. Poette C. et al 'Advanced gas cooled fast reactor preliminary design - 300 MWe project status and trends for a higher unit power selection', Proceedings of ICAPP'04 conference, Pittsburgh, PA USA, June 13-17, 2004