Behavior of Fuel and Structural Materials in Severely Damaged Reactors

Nobuaki Sato; Akira Krishima; Takayuki Sasaki

doi:10.4028/www.scientific.net/AST.94.93

Paper Titles

A Microfluidic-Assisted Fabrication of Size-Controlled Porose CeO₂ Microspheres as an Analog Production of Nuclear Fuel Beads
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Xenon Ion Irradiation Effects on a Ni-Base Ni-17Mo-7Cr Alloy
p.69

Selective Decontamination and Stable Solidification of Cs-Insoluble Ferrocyanide by Zeolites
p.75

Fabrication and Chemical Durability of Ceramic Technetium-Based Pyrochlores and Perovskites as Potential Waste Forms
p.85

Behavior of Fuel and Structural Materials in Severely Damaged Reactors
p.93

A New Matrix for Conditioning Chloride Salt Wastes from the Electrorefining of Spent Nuclear Fuel
p.97

Adsorption Materials Development for the Separation of Actinides and Specific Fission Products from High Level Waste
p.103

Progress at ANSTO on a Synroc Plant for Intermediate-Level Waste from Reactor Production of ⁹⁹Mo
p.111

Review of the Development of the Proposed Yucca Mountain Geologic Repository
p.115

HomeAdvances in Science and TechnologyAdvances in Science and Technology Vol. 94Behavior of Fuel and Structural Materials in...

Behavior of Fuel and Structural Materials in Severely Damaged Reactors

Abstract:

To study the fuel debris treatment at Fukushima Daiichi NPP, information on the behaviour of fuel and structural materials in severely damaged reactors, i.e., oxides and metals of uranium and zirconium is essential. Since sea water was introduced to the reactors, situation of fuel debris became different from that for TMI case. In this paper, phase relations of uranium and zirconium oxides were analyzed by powder XRD method at high temperatures. By the heat-treatment of the mixture of UO₂ and ZrO₂ (U:Zr=1:1) under 10 torr air, UO₂ was oxidized to U₃O₈ over 800 ^oC, The UO₂ like phase appeared again at 1350 ^oC which may be caused by the decomposition of U₃O₈. The oxidation behavior of the UO₂-ZrO₂ system was also investigated by using solid solution sample with different U/Zr ratios under different steam and oxygen pressures. The oxidation of the UO₂-ZrO₂ mixture seemed to be suppressed with decreasing U/Zr ratio. The behavior of fuel materials in the presence of seawater was also discussed as well as that for other structural materials.

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Advances in Science and Technology (Volume 94)

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93-96

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https://doi.org/10.4028/www.scientific.net/AST.94.93

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October 2014

Authors:

Nobuaki Sato*, Akira Krishima, Takayuki Sasaki

Keywords:

Fuel Debris, Nuclear Fuel, Severe Accident, Uranium Oxide, Zirconium Oxide

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