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ARTICLE

Interpolation and Extrapolation Method to Analyze Irradiation-Induced Dimensional Change Data of Graphite for Design of Core Components in Very High Temperature Reactor (VHTR)

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Pages 591-598 | Received 11 Sep 2009, Accepted 11 Feb 2010, Published online: 05 Jan 2012

References

  • Saito , S. 1994 . Design of High Temperature Engineering Test Reactor (HTTR) , JAERI 1332 Japan Atomic Energy Research Institute .
  • Fujikawa , S. , Hayashi , H. Nakazawa , T. 2004 . “Achievement of reactor outlet coolant temperature of 950_C in HTTR” . J. Nucl. Sci. Technol. , 41 : 1245 – 1254 .
  • Hoffelner , W. 2005 . “International R&D Roadmap for Generation IV-VHTR Materials Research” . In Proc. ICAPP'05 Seoul , , Korea May 15–19, 2005, Paper5206
  • Kunitomi , K. , Katanishi , S. Takada , S. 2004 . “Reactor core design of Gas Turbine High Temperature Reactor 300” . Nucl. Eng. Design , 230 : 349 – 366 .
  • Kunitomi , K. , Yan , X. Nishihara , T. 2007 . “JAEA's VHTR for hydrogen and electricity cogeneration: GTHTR300C” . Nucl. Eng. Technol. , 39 ( 1 ) : 9 – 20 .
  • Ishihara , M. , Iyoku , T. Toyota , J. 1991 . An Explanation of Design Data of the Graphite Structural Design Code for Core Components of High Temperature Engineering Test Reactor , JAERI-M 91–153 Japan Atomic Energy Research Institute . [in Japanese]
  • Snead , L. L. , Burchell , T. D. and Katoh , Y. 2008 . “Swelling of nuclear graphite and high quality carbon fiber composite under very high irradiation temperature” . J. Nucl. Mater. , 381 : 55 – 61 .
  • Burchell , T. D. 2008 . “Irradiation induced creep behavior of H-451 graphite” . J. Nucl. Mater. , 381 : 46 – 54 .
  • Haag , G. 2005 . Properties of ATR-2E Graphite and Property Changes due to Fast Neutron Irradiation , Jül-4183 Forschungszentrum Jülich .
  • Vreeling , J. A. , Wouters , O. and van der Laan , J. G. 2008 . “Graphite irradiation testing for HTR technology at the High Flux Reactor in Petten” . J. Nucl. Mater. , 381 : 68 – 75 .
  • HTTR Design Laboratory et al. 1989 . Graphite Structural Design Code for the High Temperature Engineering Test Reactor , JAERI-M 89–006 Japan Atomic Energy Research Institute . [in Japanese]
  • Shibata , T. , Eto , M. Kunimoto , E. 2009 . Draft of Standard of Graphite Core Components in High Temperature Gas-Cooled Reactor , JAEA-Research 2009–042 Japan Atomic Energy Agency .
  • Toyota , J. , Iyoku , T. Ishihara , M. 1991 . An Inspection Standard of Graphite for the High Temperature Engineering Test Reactor , JAERI-M 91–102 Japan Atomic Energy Research Institute . [in Japanese]
  • Oku , T. and Ishihara , M. 2004 . “Lifetime evaluation of graphite components for HTGRs” . Nucl. Eng. Des. , 227 ( 2 ) : 209 – 217 .
  • Ishihara , M. , Sumita , J. Shibata , T. 2004 . “Principle design and data of graphite components” . Nucl. Eng. Des. , 233 ( 1–3 ) : 251 – 260 .
  • Kelly , B. T. and Brocklehurst , J. E. 1971 . “High dose fast neutron irradiation of highly oriented pyrolytic graphite” . Carbon , 9 ( 6 ) : 783 – 789 .
  • Brocklehurst , J. E. and Kelly , B. T. 1993 . “Analysis of the dimensional changes and structural changes in polycrystalline graphite under fast neutron irradiation” . Carbon , 31 ( 1 ) : 155 – 178 .
  • Kunimoto , E. , Shibata , T. Shimazaki , Y. 2009 . Expansion of Irradiation Data by Interpolation and Extrapolation for Design of Graphite Components in High Temperature Gascooled Reactor—Evaluation on IG-110 Graphite Irradiation Data for Component Design— , JAEA-Research 2009–008 Japan Atomic Energy Agency . [in Japanese]
  • Ishiyama , S. , Burchell , T. D. , Strizak , J. P. and Eto , M. 1996 . “The effect of high fluence neutron irradiation on the properties of a finegrained isotropic nuclear graphite” . J. Nucl. Mater. , 230 : 1 – 7 .

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