DEVELOPMENT AND TESTING OF RADIATION TOLERANT CLAD MATERIALS FOR NUCLEAR FUELS

摘要

The Fuel Cycle Research and Development Program is investigating methods of burning minor actinides in a transmutation fuel. To achieve this goal, the fast reactor core materials (cladding and duct) must be able to withstand very high doses (>200 dpa design goal) while in contact with the coolant and the fuel. Thus, these materials must withstand radiation effects that promote low temperature embrittlement, high temperature helium embrittlement, swelling, accelerated creep, corrosion with the coolant, and chemical interaction with the fuel (FCCI). Research is underway that includes determining radiation effects in ferritic/martensitic steels at doses up to 200 dpa, testing and development of liners and coatings to prevent/reduce FCCI, and developing advanced alloys with improved irradiation resistance.