Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving PBR Efficiency and Testing Material Compatibility - 2004 Annual Report

Generation IV reactors will need to be intrinsically safe, having a proliferation-resistant fuel cycle and several advantages relative to existing light water reactor (LWR). They, however, must still overcome certain technical issues and the cost barrier before it can be built in the U.S. The establishment of a nuclear power cost goal of 3.3 cents/kWh is desirable in order to compete with fossil combined-cycle, gas turbine power generation. This goal requires approximately a 30 percent reduction in power cost for stateof-the-art nuclear plants. It has been demonstrated that this large cost differential can be overcome only by technology improvements that lead to a combination of better efficiency and more compatible reactor materials. The objectives of this research are (1) to develop a supercritical carbon dioxide Brayton cycle in the secondary power conversion side that can be applied to the Very-High-Temperature Gas-Cooled Reactor (VHTR), (2) to improve the plant net efficiency by using the carbon dioxide Brayton cycle, and (3) to test material compatibility at high temperatures and pressures. The reduced volumetric flow rate of carbon dioxide due to higher density compared to helium will reduce compression work, which eventually increase plant net efficiency.

[1]  S. Sherman,et al.  Evaluation of Working Fluids in an Indirect Combined Cycle in a Very High Temperature Gas-Cooled Reactor , 2006 .

[2]  S. Sherman,et al.  Thermal Hydraulic Analyses for Coupling High Temperature Gas-Cooled Reactor to Hydrogen Plant , 2006 .

[3]  P. Pickard,et al.  Thermal Hydraulic Analysis of HTGR Coupled with Hydrogen Plant , 2006 .

[4]  Robert Barner,et al.  Effects of interstage cooling on brayton cycle efficiency , 2006 .

[5]  T. Totemeier,et al.  Elevated temperature strength of fine-grained INCONEL alloy MA754 , 2005 .

[6]  D. Wilson,et al.  Thermal-Hydraulic Analyses of Heat Transfer Fluid Requirements and Characteristics for Coupling A Hydrogen Production Plant to a High-Temperature Nuclear Reactor , 2005 .

[7]  Chang Oh,et al.  Power Conversion Study for High Temperature Gas-Cooled Reactors , 2005 .

[8]  T. Totemeier,et al.  Effect of orientation on the tensile and creep properties of coarse-grained INCONEL alloy MA754 , 2005 .

[9]  L. J. Ott,et al.  The Advanced High-Temperature Reactor (AHTR) for Producing Hydrogen to Manufacture Liquid Fuels , 2004 .

[10]  D. T. Ingersoll,et al.  Status of Preconceptual Design of the Advanced High-Temperature Reactor (AHTR) , 2004 .

[11]  Richard L. Moore,et al.  Parametric Investigation of Brayton Cycle for High Temperature Gas-Cooled Reactors , 2004 .

[12]  Michel Lecomte,et al.  The Framatome ANP Indirect-Cycle Very High Temperature Reactor , 2004 .

[13]  Isabelle Sochet,et al.  Safe Hydrogen Generation by Nuclear HTR , 2004 .

[14]  Philippe Martin,et al.  Design Features and Technology Uncertainties for the Next Generation Nuclear Plant , 2004 .

[15]  Vaclav Dostal,et al.  A supercritical carbon dioxide cycle for next generation nuclear reactors , 2004 .

[16]  Isao Minatsuki,et al.  Cost and performance design approach for GTHTR300 power conversion system , 2003 .

[17]  Per F. Peterson,et al.  Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten Coolants , 2003 .

[18]  Chunyun Wang,et al.  Design, analysis and optimization of the power conversion system for the Modular Pebble Bed Reactor System , 2003 .

[19]  A. R. Jones,et al.  The microstructure and recrystallization of flow-formed oxide-dispersion-strengthened ferritic alloy: Part II. Recrystallization behavior , 2002 .

[20]  J. E. Flinn,et al.  The flow stress behavior of OFHC polycrystalline copper , 2001 .

[21]  Andrew C. Kadak,et al.  Modular Pebble Bed Reactor , 2000 .

[22]  W. King,et al.  Modifications to the microstructural topology in f.c.c. materials through thermomechanical processing , 2000 .

[23]  落合 庄治郎.  Mechanical properties of metallic composites , 1994 .

[24]  E. Ziermann.  The AVR* nuclear power facility. Progress report , 1984 .

[25]  H. Knapp,et al.  Vapor-liquid equilibria for mixtures of low-boiling substances , 1982 .

[26]  K. E. Starling,et al.  The properties of gases and liquids, Third Edition, Robert C. Reid, John M. Prausnitz and Thomas K. Sherwood, McGraw‐Hill (1977), 688 pages, $27.50 , 1978 .

[27]  R. Reid,et al.  The Properties of Gases and Liquids , 1977 .

[28]  J. Tien,et al.  The elastic modulus correction term in creep activation energies Applied to oxide dispersion strengthened superalloy , 1975 .

[29]  Henry Cohen,et al.  Gas turbine theory , 1973 .

[30]  K. Schleifenheimer.  STEADY-STATE, TRANSIENT, AND START-UP PROPERTIES OF THE AVR EXPERIMENTAL POWER STATION. , 1970 .

[31]  K. Kobe.  The properties of gases and liquids , 1959 .