GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL CO2

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GAS COOLED FAST REACTOR WITH INDIRECT SUPERCRITICAL CO2 ( gas-cooled-fast-reactor-with-indirect-supercritical-co2 )

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HEJZLARetal., AssessmentofGasCooledFastReactorwithIndirectSupercriticalCO2Cycle significantly higher stress rupture strength than the currently available alloy 800 to achieve an acceptably long lifetime for the IHX. The net plant efficiency using the reference helium direct Brayton cycle with core outlet temperature of 850°C would be between 46% to 48%, i.e., just slightly above the net efficiency of advanced SCO2 designs. Compared to a helium direct cycle option, there is another significant advantage in using indirect cycles for the GFR: the reduction of primary component size makes easier the design of the “close-containment”, a key component responsible for maintaining the backup pressure in a loss of coolant accident, which allows significant reduction of the power demand of the decay heat removal systems. In addition to the SCO2 component design issues, it is worth mentioning that operating issues, such as start-up and load variations should be also studied. In particular, for load following or cogeneration applications, it is necessary to identify adequate means to maintain high efficiency at reduced load. ACKNOWLEDGMENTS This work was supported by the U.S. DOE via Idaho Environmental and Engineering Laboratory, Sandia National Laboratory, and Argonne National Laboratory (ANL). The support via ANL was within the framework of an I- NERI bilateral project between the U.S. DOE and the French Commisariat á l’Energie Atomique (CEA). All the support is gratefully acknowledged. REFERENCES_______________________________ [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). [ 9 ] Y. Wang, V. Dostal, P. Hejzlar, “Turbine Design for Supercritical CO2 Brayton Cycle”, Proc. of GLOBAL’03, New Orleans, November 16-20, (2003). [10]V. Dostal., P. Hejzlar., M.J. Driscoll and Y. Wang., “Supercritical CO2 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 CO2 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 Comme- rcialization and Generation Cost Estimates”, HTGR-90365, August (1993). [19] Diehl H., Bodman E., “Alloy 800 Specifications in Co- mpliance with Component Requirements”, Journal of Nuclear Materials, 171, pp. 63-70, (1990). [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. [ 1 ] [ 2 ] [ 3 ] [ 4 ] [ 5 ] [ 6 ] G. Sulzer, “Verfahren zur Erzeugung von Arbeit aus Warme,” Swiss Patent CH 269599 (July 15, 1950). 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). G. Angelino, “Real Gas Effects in Carbon Dioxide Cycles”, ASME 69-GT-103, American Soc. Of Mechanical Engineers (1969). R. A. STRUB and A. J. FRIEDER, “High Pressure Indirect CO2 Closed-Cycle Design Gas Turbines”, Nuclear Gas Turbines, 51-61 (1970). V. Dostal, P. Hejzlar, M.J Driscoll, and N.E. Todreas, ”A Supercritical CO2 Brayton Cycle for Advanced Reactor Applications,” Transactions of the American Nuclear Society, 85, ( 2001). V. Dostal., P. Hejzlar , M.J Driscoll., and N.E. Todreas, ”A Supercritical CO2 Gas Turbine Power Cycle for Next Generation Nuclear Reactors”, Proc. of ICONE-10, Arlington, Virginia, April 14 – 18, (2002). 118 NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.38 NO.2 SPECIAL ISSUE ON ICAPP ‘05

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