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Program

Neutronic aspects
  • Safety aspects of IMF loaded reactors
  • Benchmark studies of uranium free inert matrix cores
  • Scenario studies for actinide transmutation
Material Science
  • Properties of inert matrix materials (e.g. spinel, zirconia)
  • Fuel concepts and fabrication of targets for transmutation of Pu and minor actinides
  • Irradiation damage in inert matrices (He, F.P.)
  • Irradiations of IMF fuel (integral experiments: Halden, HFR, JRR-3 etc.)
Panel discussion
Technical requirements for inert matrix fuels from physics scenarios

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Update 17 October 2001