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Gas Cooled Reactor Operating History

IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies ICTP – Trieste, Italy, 18-30 May 2008. Gas-Cooled Reactors –Technology Options, Operating Research Reactors and Demonstration Plant Project Initiatives J. M. Kendall Global Virtual LLC.

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Gas Cooled Reactor Operating History

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  1. IAEA-ICTP Workshop onNuclear Reaction Data forAdvanced Reactor TechnologiesICTP – Trieste, Italy, 18-30 May 2008 Gas-Cooled Reactors –Technology Options, Operating Research Reactors and Demonstration Plant Project Initiatives J. M. Kendall Global Virtual LLC -1-

  2. Gas Cooled ReactorOperating History -2-

  3. Major Technology Options Pebble Bed Prismatic Block -3-

  4. Technology OptionPebble Bed 5mm Graphite layer Coated particles imbedded in Graphite Matrix Pyrolytic Carbon Dia. 60 mm Silicon Carbide Pyrolytic Carbon Fuel Sphere Porous Carbon Buffer Half Section Dia. 0,92 mm Coated Particle Dia.0,5 mm Uranium Dioxide Fuel Kernel PBMR Pty presentations to US Nuclear Regulatory Commission, Meeting on PBMR Safety and Design Familiarization, 28 February – 2 March 2006. -4-

  5. Technology OptionPebble Bed PBMR Pty presentations to US Nuclear Regulatory Commission, Meeting on PBMR Safety and Design Familiarization, 28 February – 2 March 2006. -5-

  6. Technology OptionPebble Bed PBMR Pty presentations to US Nuclear Regulatory Commission, Meeting on PBMR Safety and Design Familiarization, 28 February – 2 March 2006. -6-

  7. Pyrolytic Carbon Silicon Carbide Porous Carbon Buffer Uranium Oxycarbide PARTICLES COMPACTS FUEL ELEMENTS Technology OptionPrismatic Block INEEL/EXT-04-02331, Reactor Physics Parametric and Depletion Studies in Support of TRISO Particle Fuel Specification for the Next Generation Nuclear Plant, September,2004. -7-

  8. Technology OptionPrismatic Block INEEL/EXT-04-02331, Reactor Physics Parametric and Depletion Studies in Support of TRISO Particle Fuel Specification for the Next Generation Nuclear Plant, September,2004. -8-

  9. Technology OptionPrismatic Block INEEL/EXT-03-00870, Rev. 1, NGNP Point Design – Results of the Initial Neutronics and Thermal-Hydraulic Assessments During FY-03, September,2003. -9-

  10. Operating Research Reactors HTR-10 Pebble Bed China HTTR Prismatic Block Japan -10-

  11. Operating Research ReactorsHTR-10 (China) Z. Daxin, Q. Zhenya, INET, Overview of the 10 MW High Temperature Gas-Cooled Reactore Test Module, Seminar on HTGR Application and Development, Beijing, 19-21 March 2001. -11-

  12. Operating Research ReactorsHTR-10 (China) 10 MWt IAEA-TECDOC-1382, Evaluation of high temperature gas cooled reactor performance: Benchmark analysis related to initial testing of the HTTR and HTR-10, November 2003. -12-

  13. Operating Research ReactorsHTR-10 (China) Z. Zhensheng, H Shuyan, INET, Structural Design Features of Ceramic Internals in HTR-10, Seminar on HTGR Application and Development, Beijing, 19-21 March 2001. -13-

  14. Operating Research ReactorsHTR-10 (China) -14- Initial Criticality December 2000

  15. Operating Research ReactorsHTTR (Japan) 30 MWt IAEA-TECDOC-1382, Evaluation of high temperature gas cooled reactor performance: Benchmark analysis related to initial testing of the HTTR and HTR-10, November 2003. -15-

  16. Operating Research ReactorsHTTR (Japan) IAEA-TECDOC-1382, Evaluation of high temperature gas cooled reactor performance: Benchmark analysis related to initial testing of the HTTR and HTR-10, November 2003. -16-

  17. Operating Research ReactorsHTTR (Japan) -17-

  18. Operating Research ReactorsHTTR (Japan) Initial Criticality November 1998 -18-

  19. Demonstration ProjectsPebble Bed and Prismatic Block • Ongoing Projects • Pebble Bed • China – HTR-PM • South Africa – PBMR • Prismatic Block or Pebble Bed • USA - NGNP • Initiatives (Prismatic Block) • US/Russia – GT-MHR Pu • Japan – GTHTR 300 -19-

  20. Demonstration ProjectsHTR-PM (China) Wu Zongxin, INET, Introduction of HTR-PM Demonstration Project, IAEA Technical Meeting on the Safety of HTGRs, Beijing, October 2007. -20-

  21. Demonstration ProjectsHTR-PM (China) • Pebble Bed • 2 Reactor/Steam Generator units at 250 MWt each • Steam Turbine-Generator output 200 Mwe • Scheduled Completion ~2013 Wu Zongxin, INET, Introduction of HTR-PM Demonstration Project, IAEA Technical Meeting on the Safety of HTGRs, Beijing, October 2007. -21-

  22. Demonstration ProjectsHTR-PM (China) Wu Zongxin, INET, Introduction of HTR-PM Demonstration Project, IAEA Technical Meeting on the Safety of HTGRs, Beijing, October 2007. -22-

  23. Demonstration ProjectsPBMR DPP (South Africa) J. Slabber, Pebble Bed Modular Reactor Project, IAEA TWG-GCR 20, Vienna, January 2007. -23-

  24. Demonstration ProjectsPBMR DPP (South Africa) • Pebble Bed • Annular reactor core 400 MWt • Direct cycle gas turbine ~175 MWe • Scheduled Completion ~2013 J. Slabber, Pebble Bed Modular Reactor Project, IAEA TWG-GCR 20, Vienna, January 2007. -24-

  25. Demonstration ProjectsPBMR DPP (South Africa) J. Slabber, Pebble Bed Modular Reactor Project, IAEA TWG-GCR 20, Vienna, January 2007. -25-

  26. Demonstration ProjectsPBMR DPP (South Africa) J. Slabber, Pebble Bed Modular Reactor Project, IAEA TWG-GCR 20, Vienna, January 2007. -26-

  27. Demonstration ProjectsNGNP (USA) INL/EXT-07-12967, Next Generation Nuclear Plant Pre-Conceptual Design Report, September 2007 -27-

  28. Demonstration ProjectsNGNP (USA) • Three competing design organizations • Westinghouse • AREVA • General Atomics • Pebble Bed or Prismatic • 500-600 MWt • Combined Electricity and Hydrogen Production • Scheduled Completion ~2018 INL/EXT-07-12967, Next Generation Nuclear Plant Pre-Conceptual Design Report, September 2007 -28-

  29. Demonstration ProjectsNGNP (USA) • Westinghouse • Pebble Bed • Hydrogen production topping cycle • Steam turbine bottoming cycle INL/EXT-07-12967, Next Generation Nuclear Plant Pre-Conceptual Design Report, September 2007 -29-

  30. Demonstration ProjectsNGNP (USA) • AREVA • Prismatic • Parallel Hydrogen production cycle • Parallel gas turbine with steam turbine bottoming cycle INL/EXT-07-12967, Next Generation Nuclear Plant Pre-Conceptual Design Report, September 2007 -30-

  31. Demonstration ProjectsNGNP (USA) • General Atomics - Prismatic • Direct cycle gas turbine • Parallel Hydrogen production cycle INL/EXT-07-12967, Next Generation Nuclear Plant Pre-Conceptual Design Report, September 2007 -31-

  32. Demonstration ProjectsNGNP (USA) General Atomics Prismatic AREVA Prismatic Westinghouse Pebble Bed INL/EXT-07-12967, Next Generation Nuclear Plant Pre-Conceptual Design Report, September 2007 -32-

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