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
スポンサーリンク
概要
著者
-
Yajima Seishi
Division of Chemistry Japan Atomic Energy Research Institute
-
Ichiba Sumio
Division of Chemistry Japan Atomic Energy Research Institute
-
Kamemoto Yuichiro
Division of Chemistry Japan Atomic Energy Research Institute
-
Shiba Koreyuki
Division of Chemistry Japan Atomic Energy Research Institute
-
Yajima S.
Division of Chemistry 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