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This project will examine inert matrix fuels containing ZrO2 and MgO as the inert matrix, with the relative amount of MgO varied from 30% to 70% in ZrO2. Reactor physics calculations will be used to examine suitable quantities of burnable poisons from the candidate elements Gd, Er, or Hf with reactor grade Pu providing the fissile component, with up to 10% of 239Pu. Ceramics will be synthesized and characterized based on the reactor physics results. The solubility the fuel ceramics, in reactor conditions, reprocessing conditions, and repository conditions, will be investigated in a manner to provide thermodynamic data necessary for modeling.
The fuel matrix will be designed based on neutronic properties, repository behavior, and reprocessing characteristics. The matrix should be as neutron transparent as possible. Burnable poisons will be used to maintain constant reactivity. The matrix should also act as a suitable host form for fission products and actinides in a repository environment. Finally, the matrix should be compatible with reprocessing schemes under development in the advanced fuel cycle.
In this quarter work was performed on synthesis of ceramics and reactor physics calculation. The work was build upon the results from the previous quarter. The fuel synthesis focused on the conditions and ratios of inert matrix material necessary for synthesis of a single phase. The reactor physics calculations examined the Pu loading necessary to achieve industry standard fuel cycle lengths and the matrix composition effect on Pu loading.
Magnesium oxide; Mixed oxide fuels (Nuclear engineering); Nuclear chemistry; Nuclear fuels; Plutonium; Solid oxide fuel cells; Zirconium oxide
Mixed oxide fuels (Nuclear engineering); Nuclear fuels; Solid oxide fuel cells--Design and construction
Nuclear | Oil, Gas, and Energy | Physical Chemistry
Dissolution, Reactor, and Environmental Behavior of ZrO2-MgO Inert Fuel Matrix: Quarterly Report, October 2004 to December 2004.
Available at: https://digitalscholarship.unlv.edu/hrc_trp_fuels/61