Thoria-based cermet nuclear fuel : neutronics fuel design and fuel cycle analysis.

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Cermet nuclear fuel has been demonstrated to have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle produces intriguing options for advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application ... continued below

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12 pages

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Downar, T.J.; McDeavitt, S.M.; Revankar, S.T.; Solomon, A.A. & Kim, T.K. January 9, 2002.

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Description

Cermet nuclear fuel has been demonstrated to have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle produces intriguing options for advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application of this new fuel form. This paper will first describes the fuel thermal performance model developed for the analysis of dispersion metal matrix fuels. The model is then applied to the design and analysis of thorium/uranium/zirconium metal-matrix fuel pins for light-water reactors using neutronic simulation methods.

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12 pages

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  • 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA (US), 04/14/2002--04/18/2002

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  • Report No.: ANL/CMT/CP-106455
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 793900
  • Archival Resource Key: ark:/67531/metadc736812

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • January 9, 2002

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  • Oct. 19, 2015, 7:39 p.m.

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  • March 24, 2016, 2:51 p.m.

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Downar, T.J.; McDeavitt, S.M.; Revankar, S.T.; Solomon, A.A. & Kim, T.K. Thoria-based cermet nuclear fuel : neutronics fuel design and fuel cycle analysis., article, January 9, 2002; Illinois. (digital.library.unt.edu/ark:/67531/metadc736812/: accessed October 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.