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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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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

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major technology options
Major Technology Options

Pebble Bed

Prismatic Block

-3-

technology option pebble bed
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.

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technology option pebble bed1
Technology OptionPebble Bed

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

-5-

technology option pebble bed2
Technology OptionPebble Bed

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

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technology option prismatic block

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.

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technology option prismatic block1
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.

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technology option prismatic block2
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.

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operating research reactors
Operating Research Reactors

HTR-10

Pebble Bed

China

HTTR

Prismatic Block

Japan

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operating research reactors htr 10 china
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.

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operating research reactors htr 10 china1
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.

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operating research reactors htr 10 china2
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.

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operating research reactors htr 10 china3
Operating Research ReactorsHTR-10 (China)

-14-

Initial Criticality December 2000

operating research reactors httr japan
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-

operating research reactors httr japan1
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.

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operating research reactors httr japan3
Operating Research ReactorsHTTR (Japan)

Initial Criticality November 1998

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demonstration projects pebble bed and prismatic block
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

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demonstration projects htr pm china
Demonstration ProjectsHTR-PM (China)

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

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demonstration projects htr pm china1
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-

demonstration projects htr pm china2
Demonstration ProjectsHTR-PM (China)

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

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demonstration projects pbmr dpp south africa
Demonstration ProjectsPBMR DPP (South Africa)

J. Slabber, Pebble Bed Modular Reactor Project, IAEA TWG-GCR 20, Vienna, January 2007.

-23-

demonstration projects pbmr dpp south africa1
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-

demonstration projects pbmr dpp south africa2
Demonstration ProjectsPBMR DPP (South Africa)

J. Slabber, Pebble Bed Modular Reactor Project, IAEA TWG-GCR 20, Vienna, January 2007.

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demonstration projects pbmr dpp south africa3
Demonstration ProjectsPBMR DPP (South Africa)

J. Slabber, Pebble Bed Modular Reactor Project, IAEA TWG-GCR 20, Vienna, January 2007.

-26-

demonstration projects ngnp usa
Demonstration ProjectsNGNP (USA)

INL/EXT-07-12967, Next Generation Nuclear Plant Pre-Conceptual Design Report, September 2007

-27-

demonstration projects ngnp usa1
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-

demonstration projects ngnp usa2
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-

demonstration projects ngnp usa3
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-

demonstration projects ngnp usa4
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-

demonstration projects ngnp usa5
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

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