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[IMF - Main] > [Program]
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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