Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May 2008

Transcription

1 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May 2008 Gas-Cooled Reactors Technology Options, Operating Research Reactors and Demonstration Plant Project Initiatives. J.M. Kendall Global Virtual LLC Prescott USA

2 IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies ICTP Trieste, Italy, May 2008 Gas-Cooled Reactors Technology Options, Operating Research Reactors and Demonstration Plant Project Initiatives J. M. Kendall Global Virtual LLC -1-

3 Gas Cooled Reactor Operating History Dragon Peach Bottom I Fort St. Vrain AVR THTR UK USA USA Germany Germany Rods Rods Blocks Pebbles Pebbles MWt 115 MWt 842 MWt 46 MWt 750 MWt 40 MWe 330 MWe 15 MWe 296 MWe C C C C C -2-

4 Major Technology Options Pebble Bed Prismatic Block -3-

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

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

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

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

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

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

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

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

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

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

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

16 Operating Research Reactors HTTR (Japan) 30 MWt -15- 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 Operating Research Reactors HTTR (Japan) -16- 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.

18 Operating Research Reactors HTTR (Japan) -17-

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

20 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

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

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

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

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

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

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

27 Demonstration Projects PBMR DPP (South Africa) Reactivity Control System (RCS) Reserve Shutdown System (RSS) Core Structures (CS) Reactor Pressure Vessel Core Inlet Pipe connection Core Barrel Reactor Pressure Vessel (RPV) Side Reflector Fuel Core Core Outlet Pipe connection Gas Riser Channels Centre Reflector SAS Channels Control Rod Channels Core Inlet Pipe connection Core Unloading Device (CUD) -26- J. Slabber, Pebble Bed Modular Reactor Project, IAEA TWG-GCR 20, Vienna, January 2007.

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

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

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

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

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

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