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This progress report presents results of analysis performed within the framework of “Dissolution, Reactor, and Environmental Behavior of ZrO2-MgO Inert Fuel Matrix” project managed by University of Nevada at Las Vegas, Harry Reid Center for Environmental Studies.
The BGU working program includes the following four tasks:
1. Benchmark of computational tools
2. Determination of fissile Pu loading
3. Evaluation of burnable poison designs
4. Evaluation of reactivity feedback coefficients
This progress report presents the results of Task 1. The main objective of this task is to confirm the validity of the ELCOS 1 code system for inert matrix fuel analysis applied to a standard PWR fuel design. Computer codes used are described briefly in the subsequent section. We performed a series of benchmark calculations, which were designed to include the possible range of fuel compositions.
We considered a unit fuel cell and 2-D fuel assembly geometries. The main computer code of the ELCOS system for assembly calculations – BOXER 2, was tested against MCNP code with two different cross-section libraries.
Magnesium oxide; Mixed oxide fuels (Nuclear engineering); Nuclear chemistry; Nuclear fuels; Plutonium; Solid oxide fuel cells; Zirconium oxide
Nuclear | Nuclear Engineering | Oil, Gas, and Energy | Radiochemistry
Dissolution, Reactor, and Environmental Behavior of ZrO2-MgO Inert Fuel Matrix: Neutronic Evaluation of ZrO2-MgO Inert Fuels.
Available at: http://digitalscholarship.unlv.edu/hrc_trp_fuels/81