Chemical State of Fission Tellurium Released from Irradiated UO<SUB>2</SUB> and UO<SUB>2</SUB>-Graphite Mixtures

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概要

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• The chemical state of fission Te released from ceramic fuels was studied by means of the thermochromatograph. In inert atmosphere, the fission Te was found to be released in the form of metal, but in the presence of oxygen, it readily reacted therewith to form TeO<SUB>2</SUB>. The chemical state of I released from Te and TeO<SUB>2</SUB>, was also determined.

著者

• Shiba Koreyuki

  Division of Chemistry Japan Atomic Energy Research Institute

• YAJIMA Seishi

  Research Institute for Iron, Steel and Other Metals Tohoku University

• HANADA Muneo

  Division of Nuclear Fuel Research, Japan Atomic Energy Research Institute

関連論文

• Lithium Isotope Separation by Displacement Chromatography Using Cryptand Resin
• Studies of Ceramic Fuels with Use of Fission Gas Release Loop, (IV) : Fission Gas Release from Uranium Carbide in the Presence of Trace Amounts of Water Vapor
• Chemical State of Fission Tellurium Released from Irradiated UO2 and UO2-Graphite Mixtures
• Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (II) : Measurement of Gamma-ray Spectrum of Fission Gases
• Studies on Ceramic Fuels with the Use of Fission Gas Release Loop, (III) : Neutron Flux Monitoring in Specimen Chamber of FGRL by Counting Nitrogen-16 Generated 16O(n, p) 16N Reaction in Primary Cooling Water
• The Behavior of Fission Products Captured in Graphite Powder by Nuclear Recoil. IV. Further Studies on the Diffusion of Xenon-133 in Graphite
• The Behavior of Fission Products Captured in Graphite Powder by Nuclear Recoil. III. Diffusion of Iodine-133 and Tellurium-132 in Graphite at High Temperatures
• The Use of Radioactive Fission Product Rare Gases for the Study of the Change in Crystal Structure
• Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (I):Fission Gas Release from UO2-Graphite Mixture during Irradiation

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