Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (I):Fission Gas Release from UO<SUB>2</SUB>-Graphite Mixture during Irradiation

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概要

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• Fission gas release from a UO<SUB>2</SUB>-graphite mixture was studied during irradiation with the use of the Fission Gas Release Loop in the JRR-3 reactor. The release rates of fission krypton and xenon increased proportionally with neutron flux (6×10<SUP>10</SUP>-6×10<SUP>12</SUP>n/cm<SUP>2</SUP>•sec) and exponentially with temperature (400°-1, 000°C). A burst of fission gas was observed when the specimen was abruptly heated to a higher temperature. These results can be explained by a mechanism whereby fission gas is trapped in defects created in graphite by fission fragments and released through annealing of the defects.

• 一般社団法人 日本原子力学会の論文

著者

• Kamemoto Yuichiro

  Division of Chemistry Japan Atomic Energy Research Institute

• Yamagishi Shigeru

  Division of Chemistry Japan Atomic Energy Research Institute

• TAKAHASHI Yoshihisa

  Division of Fuel Research and Development, Japan Atomic Energy Research Institute

• TANIFUJI Takaaki

  Division of Fuel Research and Development, Japan Atomic Energy Research Institute

• OMORI Shunzo

  Division of Fuel Research and Development, Japan Atomic Energy Research Institute

• HAND Muneo

  Division of Fuel Research and Development, Japan Atomic Energy Research Institute

• YAJIMA Seishi

  Research Institute for Iron, Steel and Other Metals Tohoku University

• YAJIMA Seishi

  Research Institute for Iron, Steel and Other Metals, Tohoku University

• FUKUDA Takeshi

  Division of Fuel Research and Development, Japan Atomic Energy Research Institute

関連論文

• 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
• Transjugular intrahepatic portosystemic shunt versus paracentesis plus albumin in patients with refractory ascites who have good hepatic and renal function : a prospective randomized trial
• 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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