Isotope Exchange Capacity on Li_4SiO_4 and Comparison of Tritium Inventory in Various Solid Breeder Blankets
スポンサーリンク
概要
- 論文の詳細を見る
It has been pointed out by the present authors that it is essential to understand such mass transfer steps as diffusion of tritium in the grain of a breeder material, absorption of water vapor into bulk of the grain, adsorption of water on surface of the grain, and exchange capacity of tritium to be trapped to surface of the grain together with two types of isotope exchange reactions for evaluation of the tritium inventory in a solid breeder blanket under various conditions. The isotope exchange capacity on the Li4SiO4 surface is experimentally obtained in this study. Most of the properties required for evaluation of the tritium inventory for various blanket materials have been already quantified by the present authors. Then it has become possible to compare the tritium inventory in solid breeder blankets packed with either Li2O, LiAlO2, Li2ZrO3, Li2TiO3 or Li4SiO4 using the calculation model previously presented by the present authors.
- 一般社団法人 日本原子力学会の論文
- 2001-11-25
著者
-
西川 正史
九州大学大学院総合理工学研究院
-
西川 正史
九大総理工
-
西川 正史
九州大学大学院総合理工学研究科
-
Nishikawa Masabumi
Department Of Advanced Energy Engineering Science Interdisciplinary Graduate School Of Engineering S
-
Nakashima Noriaki
Department Of Energy Science Graduate School Of Engineering Science Kyushu University
-
HASHIMOTO Kazuhisa
Department of Energy Science, Graduate School of Engineering Science, Kyushu University
-
BELOGLAZOV Serguei
Department of Energy Science, Graduate School of Engineering Science, Kyushu University
-
Beloglazov Serguei
Department Of Energy Science Graduate School Of Engineering Science Kyushu University
-
Hashimoto Kazuhisa
Department Of Energy Science Graduate School Of Engineering Science Kyushu University
関連論文
- 4.核融合炉ブランケット材中のトリチウム移動現象解明と新規回収プロセス開発の研究(核融合炉実現を目指したトリチウム研究の新展開)
- 3.燃料システム内トリチウム挙動(核融合炉内外におけるトリチウムの挙動)
- 第17期日本学術会議核科学総合研究連絡委員会核融合専門委員会報告(平成12年5月29日)核融合炉工学の再構築と体系化について
- FRC/DD-^3He アドバンス炉の概念
- ブランケット工学の最前線
- 施設におけるトリチウム水の気液間移行挙動 (「トリチウム安全理工学」専門研究会報告書)
- 触媒金属を担持させたセラミック増殖材からのトリチウム放出率の増加
- 6. 炉チェンバー・炉システム設計(高速点火レーザー核融合発電プラント(KOYO-Fast)の概念設計)
- ICONE11-36152 NOBLE GASES RECOVERY IN SPENT NUCLEAR FUEL REPROCESSING CYCLE
- Adsorption of Noble Gases on H-Mordenite
- Dynamics of Adsorption of Kr and Xe on MS5A and Activated Charcoal
- Tritium Release from Improved Ceramic Tritium Breeder with Catalytic Function
- Removal of Carbon Dioxide in Reprocessing Spent Nuclear Fuel off Gas by Adsorption
- Adsorption Equilibria of Krypton, Xenon, Nitrogen and Their Mixtures on Molecular Sieve 5A and Activated Charcoal
- Development of an Improved Ceramic Tritium Breeder, -Ceramic Breeder with Catalytic Function
- パラジウム充填層を用いた1,2,3,4塔システムによる水素同位体分離の実験的比較
- Hydrogen Isotope Separation by Self-displacement Chromatofraphy Using Palladium Partickes
- Mist Formation in a Water Vapor Cold Trap and Evaluation of Its Removal Rate
- 減圧下の水平冷却面上における結霜成長
- 液体Li,Li-Pd,溶融塩ブランケットからのトリチウム回収
- Mass Transfer Behavior of Tritium from Air to Water through the Water Surface
- 材料表面のトリチウムの挙動に与える水蒸気の影響
- S702 固体ブランケット内におけるトリチウム移行挙動(核融合炉環境におけるトリチウム挙動とリサイクル技術, (社) プラズマ・核融合学会第21回年会)
- 2 ITERに向けた核融合炉燃料システムにおけるトリチウム動態(シンポジウムIII : 核融合炉内外におけるトリチウム動態)
- 水素同位体分離研究の現状
- A MULTILAYER MODEL FOR ADSORPTION OF WATER ON ACTIVATED ALUMINA IN RELATION TO ADSORPTION POTENTIAL
- トリチウムから見た核融合炉の成立性
- Isotope Effect in Hydrogen Isotope Exchange Reaction on First Wall Materials
- Isotope Exchange Capacity on Li_4SiO_4 and Comparison of Tritium Inventory in Various Solid Breeder Blankets
- 水素エネルギーシステムの開発課題と現状
- 1. はじめに (核融合炉内外におけるトリチウムのメインテナンスと廃棄物処理)
- II-5 D-^3He炉におけるトリチウム
- 8. D-^3He核融合の燃料システム( D-^3He核融合とその開発課題)
- 5.トリチウムの安全取扱技術(核融合炉でのトリチウム技術開発)
- FROST FORMATION UNDER DIFFERENT GASEOUS ATMOSPHERES
- Solubility and Separation Factor of Protium-Deuterium Binary Component System in Palladium
- Permeation Rate of Hydrogen Isotopes through Palladium-Silver Alloy
- Hydrogen Isotope Separation by Displacement Chromatography with Palladium
- DEPENDENCE OF CHARACTERISTIC FACTOR FOR DUBININ-ASTAKHOV EXPRESSION ON PERMITTIVITY IN RELATION WITH TEMPERATURE IN POLAR ADSORPTION SYSTEM
- Calculation of Breakthrough Curve of Multicomponent Hydrogen Isotopes Using Cryosorption Column
- トリチウムの研究課題 (磁気閉じ込め核融合炉の実現と支える先駆技術) -- (燃料サイクルとブランケット)
- Adsorption and Desorption Behavior of Tritiated Water on the Piping Materials
- 01aB04 高速点火レーザー核融合炉KOYO-Fの概念設計3,炉システム/燃料系(新概念、炉設計)
- 2.D-T核融合炉のトリチウム(核融合炉実現を目指したトリチウム研究の新展開)
- RV-1 核融合エネルギー開発に関わる水素製造とトリチウム研究の展望
- HEAT TRANSFER TO COOLING COIL ACTING AS ROTATING IMPELLER IN HIGHLY VISCOUS LIQUIDS
- Catalytic oxidation of tritium in wet gas.
- Drop Size Distribution in a Liquid-Liquid Phase Mixing Vessel
- Enrichment and volume reduction of tritiated water using electrolysis cell having hydrogen permeable cathode.
- Recovery of tritium in inert gas by precious metal catalyst supported by hydrophilic substrate.
- Fractional treatment of spent scintillation cocktail with low level tritium by azeotropic distillation.
- Oxidation of tritium gas in glovebox atmosphere using CuO column.
- Analytical Method of Calibration for Moisture Sensor of Capacitor Type.
- TURBULENCE IN NON-BAFFLED MIXING VESSEL
- Gas absorption in a multi-stage gas-liquid spouted vessel.
- Studies on gas hold-up in gas-liquid spouted vessel.
- Gas absorption in an aerated mixing vessel with multi-stage impellers.
- Scale-up of liquid-liquid phase mixing vessel.
- POWER CONSUMPTION OF MIXING IMPELLERS IN PSEUDOPLASTIC LIQUIDS
- Gas absorption in aerated mixing vessels with non-Newtonian liquid.
- HEAT TRANSFER TO VESSEL WALL BY HELICAL RIBBON IMPELLER IN HIGHLY VISCOUS LIQUIDS
- Studies of bubble size distribution in gas-liquid spouted vessel.
- Turbulence energy spectra in baffled mixing vessels.