Power conversion system considerations for a high efficiency small modular nuclear gas turbine combined cycle power plant concept (NGTCC)

Abstract The power conversion system (PCS) in the proposed small modular combined cycle nuclear gas turbine plant is based on the coupling of a non-intercooled topping helium Brayton direct closed-cycle gas turbine and a single-reheat supercritical steam Rankine bottoming cycle. The nuclear heat source (with a thermal rating of 350 MWt) is a helium cooled and graphite moderated very high temperature reactor (VHTR) embodying an assembly of prismatic fuel elements. Based on a reactor outlet (and gas turbine inlet) temperature of 95 °C, the module electrical power output is 180 MWe (50 and 130 MWe from the gas and steam turbines respectively) with an estimated plant efficiency of 51.5 percent. The design and development of the proposed nuclear gas turbine combined cycle (NGTCC) concept would benefit from established technology bases. With the inclusion of a process heat extraction module embodying a compact steam-to-steam re-boiler the proposed plant concept could operate in a cogeneration mode, namely generating electrical power plus providing a supply of uncontaminated process steam to various industrial users. This paper addresses projected HTR to VHTR plant evolution, thermodynamic cycle selection, plant performance, tentative arrangement of the combined cycle PCS, component design considerations and their technology bases, and major development requirements. The NGTCC is an advanced long-term helium cooled reactor concept, and a single module demonstration plant may be realizable by say circa 2030, this leading to commercial operation of multi-module plants, and paving the way for future very high temperature nuclear process heat plants in the middle decades of the 21st century.

[1]  A. C. Millunzi,et al.  The modular high temperature gas-cooled reactor (MHTGR) in the U.S. , 1986 .

[2]  Colin F. McDonald,et al.  Helium turbomachinery operating experience from gas turbine power plants and test facilities , 2012 .

[3]  F. J. Smith,et al.  Tritium permeation through steam generator materials , 1975 .

[4]  Michel Lecomte,et al.  ANTARES: The HTR/VHTR project at Framatome ANP , 2006 .

[5]  Yang Xu,et al.  Technical design and principle test of active magnetic bearings for the turbine compressor of HTR-10GT , 2012 .

[6]  Colin F. McDonald,et al.  Turbomachinery Design Considerations for the Nuclear HTGR-GT Power Plant , 1980 .

[7]  Colin G. McDonald Power Conversion System Considerations for an Advanced Nuclear Gas Turbine (GT-VHTR) CHHP Demonstration Plant Concept , 2010 .

[8]  H. Haselbacher,et al.  Cooling and insulating problems in a high temperature helium test facility , 1984 .

[9]  Colin F. McDonald,et al.  Nuclear refinery—advanced energy complex , 1992 .

[10]  Kazuhiko Kunitomi,et al.  Aerodynamic Design, Model Test, and CFD Analysis for a Multistage Axial Helium Compressor , 2008 .

[11]  R. Ng,et al.  Design of major components for the modular high-temperature gas-cooled reactor , 1988 .

[12]  S. F. Smith A Simple Correlation of Turbine Efficiency , 1965, The Journal of the Royal Aeronautical Society.

[13]  W. Endres Large Helium Turbines for Nuclear Power Plants , 1970 .

[14]  Wolfgang Tietsch,et al.  State of the Art of Helium Heat Exchanger Development for Future HTR-Projects , 2008 .

[15]  W. A. Simon,et al.  The gas-turbine modular helium reactor , 2004 .

[16]  G. H. Lohnert,et al.  Technical design features and essentiaL safety-related properties of the HTR-module , 1990 .

[17]  U. Okapuu,et al.  A Mean Line Prediction Method for Axial Flow Turbine Efficiency , 1982 .

[18]  Kazuhiko Kunitomi,et al.  Control Strategies for VHTR Gas-Turbine System With Dry Cooling , 2012 .

[19]  C. Mcdonald The nuclear closed-cycle gas turbine /GT-HTGR/ - A utility power plant for the year 2000 , 1978 .

[20]  Kazuhiko Kunitomi,et al.  Japan's future HTR—the GTHTR300 , 2004 .

[21]  C. Marnet,et al.  The AVR power plant in its last year of operation , 1991 .

[22]  M Casey A mean line prediction method for estimating the performance characteristic of an axial compressor stage. , 1987 .

[23]  Colin F. McDonald,et al.  The key role of heat exchangers in advanced gas-cooled reactor plants , 1994 .

[24]  Arkal Shenoy,et al.  Steam Cycle Modular Helium Reactor , 2012 .

[25]  Chris Ellis,et al.  Conceptual Design of the NGNP Reactor System , 2012 .

[26]  P. Calderoni,et al.  High-temperature Hydrogen Permeation in Nickel Alloys , 2010 .

[27]  C. F. McDonald,et al.  Steam generator design considerations for modular HTGR plant , 1986 .

[28]  Scott R. Penfield Development of the Steam Cycle-Modular Helium Reactor Steam Utilization System for High-Efficiency Cogeneration , 2012 .

[29]  Gunter H. Lohnert,et al.  The Modular High-Temperature Reactor , 1983 .

[30]  O. E. Baljé,et al.  Turbomachines—A Guide to Design Selection and Theory , 1981 .

[31]  N. G. Kodochigov,et al.  Rotor scale model tests for power conversion unit of GT-MHR , 2012 .

[32]  C. F. McDonald,et al.  The Nuclear Gas Turbine-A Perspective on a Long-Term Advanced Technology HTGR Plant Option , 1982 .

[33]  Shigeaki Nakagawa,et al.  Achievement of Reactor-Outlet Coolant Temperature of 950°C in HTTR , 2004 .

[34]  Kazuhiko Kunitomi,et al.  Design Improvements of Power Conversion System of Gas Turbine High Temperature Reactor (GTHTR300) , 2004 .

[35]  Zongxin Wu,et al.  The design features of the HTR-10 , 2002 .

[36]  Kazuhiko Kunitomi,et al.  GTHTR300 design and development , 2003 .

[37]  R. N. Quade,et al.  The design of the Fort St. Vrain steam generators , 1974 .