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-1- IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies ICTP – Trieste, Italy, 18-30 May 2008 Gas-Cooled Reactors –Technology.

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Presentation on theme: "-1- IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies ICTP – Trieste, Italy, 18-30 May 2008 Gas-Cooled Reactors –Technology."— Presentation transcript:

1 -1- 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

2 -2- Gas Cooled Reactor Operating History

3 -3- Major Technology Options Pebble Bed Prismatic Block

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

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

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

7 -7- Technology Option Prismatic Block Uranium Oxycarbide Porous Carbon Buffer Silicon Carbide Pyrolytic Carbon PARTICLESCOMPACTSFUEL ELEMENTS 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 -8- Technology Option Prismatic 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.

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

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

11 -11- Operating Research Reactors HTR-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.

12 -12- Operating Research Reactors HTR-10 (China) 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. 10 MWt

13 -13- Operating Research Reactors HTR-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.

14 -14- Operating Research Reactors HTR-10 (China) Initial Criticality December 2000

15 -15- Operating Research Reactors HTTR (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. 30 MWt

16 -16- Operating Research Reactors HTTR (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.

17 -17- Operating Research Reactors HTTR (Japan)

18 -18- Operating Research Reactors HTTR (Japan) Initial Criticality November 1998

19 -19- Demonstration Projects Pebble 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

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

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

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

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

24 -24- Demonstration Projects PBMR 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.

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

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

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

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

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

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

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

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

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