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Department Of Applied Quantum Physics And Nuclear Engineering Division Of Engineering Graduate Schoo | 論文
- Thermochemical Prediction of Chemical Form Distributions of Fission Products in LWR Oxide Fuels Irradiated to High Burnup
- Thermochemical Prediction of Chemical Form Distributions of Fission Products in LWR Mixed Oxide Fuels
- Behavior of Fission Products Zirconium and Barium in Fast Reactor Fuel Irradiated to High Burnup
- Corrosion Behavior of a Powdered Simulated Nuclear Waste Glass in the Presence of Bentonite.
- Penertration behavior of cesium in oxide film growing on surface of stainless steel under condition of high oxygen potential.
- Volumetric change of simulated radioactive waste glass irradiated by electron accelerator.
- Determination of heat capacity of simulated radioactive waste glasses by drop calorimetry.
- Preparation of thorium-uranium mixed oxide pellets.
- Effect of grain size of stainless steel on oxidation rate under oxygen pressure controlled by Mo/MoO2 oxygen buffer.