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ARTICLE

Fabrication of Sintered Annular Fuel Pellet for HANARO Irradiation Test

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Pages 345-350 | Received 25 Jun 2009, Accepted 14 Dec 2009, Published online: 05 Jan 2012

References

  • Kazimi , M. S. 2002 . High Performance Fuel Design for Next Generation PWRs: 1st Annual Report , Report No. MIT-NFC-PR- 048
  • Kazimi , M. S. and Hejzlar , P. 2003 . High Performance Fuel Design for Next Generation PWRs: 2nd Annual Report , Report No. MITNFC-PR-058
  • Kazimi , M. S. and Hejzlar , P. 2004 . High Performance Fuel Design for Next Generation PWRs: 3rd Annual Report , Report No. MITNFC-PR-068
  • Matzie , R. 2006 . “How to increase LWR power density” . In Proc. 2006 Int. Congress on Advances in Nuclear Power Plants Reno, NV , , USA Jun. 4–8, 2006
  • Hejzlar , P. and Kazimi , M. S. 2007 . “Annular fuel for high-powerdensity pressurized water reactors: Motivation and overview” . Nucl. Technol. , 160 : 2 – 15 . [1]
  • Yang , Y. S. , Bae , K. M. , Shin , C. H. , Chun , T. H. , Bang , J. G. and Song , K. W. 2007 . “Conceptual design of OPR-1000 compatible annular fuel assembly” . In Proc. 2007 Int. Congress on Advances in Nuclear Power Plants , Nice Acropolis, France, May 13–18, 2007 [CD-ROM]
  • Feng , D. , Hejzlar , P. and Kazimi , M. S. 2007 . “Thermal-hydraulic design of high-power-density annular fuel in PWRs” . Nucl. Technol. , 160 : 16 – 44 . [1]
  • Hagrman , D. T. 1993 . MATPRO—A Library of Materials Properties for Light-Water-Reactor Accident Analysis , SCDAP/RELAP5/MOD3.1 Code Manual, NUREG/CR-6150 EGG- 2720 U.S. Nuclear Regulatory Commission .
  • Uffelen , P. V. 2006 . Modelling of Nuclear Fuel Behaviour , Report No. EUR 22321 EN
  • 2005 . Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Anlaysis of Nuclear-Grade Uranium Dioxide Powders and Pellets , ASTM C696–99
  • Delette , G. , Sornay , P. and Blancher , J. 2004 . “Finite element modelling of the pressing of nuclear oxide powders to predict the shape of LWR fuel pellets after die compaction and sintering” . In Advanced Fuel Pellet Materials and Design for Water Cooled Reactors , IAEA-TECDOC-1416, IAEA 21 – 30 .
  • Yanai , K. , Hirai , M. , Ishikawa , T. , Ishizaki , J. and Saitoh , H. 1998 . “An analysis of density distribution in UO2 green pellet by finite element method” . J. Nucl. Mater. , 257 ( 3 ) : 318 – 330 .
  • 2006 . Standard Specification for Sintered Uranium Dioxide Pellets , ASTM C776–06
  • Maier , G. , Assmann , H. and Doerr , W. 1988 . “Resinter testing in relation to in-pile densification” . J. Nucl. Mater. , 153 : 213 – 220 .

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