Design Study of Feasible Water Detritiation Systems for Fusion Reactor of ITER Scale

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3.大量トリチウム取り扱いに関わる研究成果(2) : 核融合炉燃料システムの構築に向けて,日米協力の進展(大量トリチウム取り扱い技術開発30年の成果と今後の課題)
6.トリチウムの閉じ込めに関わる高濃度トリチウム水および有機物の化学的現象の解明(核融合炉実現を目指したトリチウム研究の新展開)
Application of Tail Subtraction Technique with Particle Identification to a Stacked Spectrometer for Intermediate Energy Protons
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大量トリチウム取り扱いに関わる研究成果 (2) : 核融合炉燃料システムの構築に向けて, 日米協力の進展
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Caspase-Independent Cell Death and Mitochondrial Disruptions Observed in the Apaf1-Deficient Cells^1
トリチウム安全性試験装置(CATS)を用いた室内でのトリチウム挙動 (「水素同位体の環境移行機構」京都大学原子炉実験所専門研究会報告(平成11年))
トリチウム挙動シミュレーションコード(TBEHAVIOR)の実規模トリチウムハンドリング建屋への適用性
核融合炉トリチウム水処理システムの研究開発動向
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A Steady-state Simulation Model of Gas Separation System by Hollow-filament Type Membrane Module
Influence of Framework Silica-to-Alumina Ratio on the Tritiated Water Adsorption and Desorption Characteristics of NaX and NaY Zeolites
Design Study of Feasible Water Detritiation Systems for Fusion Reactor of ITER Scale
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Application of Pressure Swing Adsorption to Water Detritiation Process
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ANALYSIS OF CHARACTERISTICS OF CRYOGENIC DISTILLATION COLUMN IN SEPARATION OF HYDROGEN ISOTOPES
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5.トリチウムシステム(核融合炉実現を目指したトリチウム研究の新展開)
Experimental Study for Characteristics of Cryogenic Distillation Column Having Feedback Stream with H-D-T System.
Mass Transfer in Cryogenic Distillation Column Separating Hydrogen Isotopes.

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