Numerical Estimation Method of the Hydrogen Isotope Inventory in the Hydrogen Isotope Separation System for Fusion Reactor

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概要

• 論文の詳細を見る

• In the fuel cycle system of the ITER, a large fraction of tritium inventory is expected to be in the cryogenic distillation columns of the hydrogen isotope separation system (ISS). Therefore, the numerical estimation method of hydrogen isotopes inventory in the ISS with high precision is strongly required from safety point of view. Two series of experiments were performed to establish the numerical estimation method of the overall hydrogen isotope inventory in the ISS at steady state using ITER-scale large cryogenic distillation columns at the Tritium Systems Test Assembly in the Los Alamos National Laboratory under the US-Japan collaboration on tritium safety engineering. As a result of experiments, it was confirmed that the hydrogen isotope inventory in a cryogenic distillation column was estimated by the numerical estimation method proposed in this work with enough high precision from the engineering point of view, and it was proved that this method was applied for the ITER-scale cryogenic distillation columns. The precision of this estimation method was found to be almost independent on the composition profile in columns, and especially the liquid holdup ratio of deuterium to the volume of the column was less influential in the inner diameter of the packed section. In addition, the gaseous inventory in an ITER-scale cryogenic distillation column was found to have considerable impact on the total amount of holdup of the column.

• 一般社団法人 日本原子力学会の論文
• 2002-06-25

著者

• 岩井 保則

  日本原子力研究開発機構核融合研究開発部門トリチウム工学研究グループ

• IWAI Yasunori

  Tritium Engineering Laboratory, Japan Atomic Energy Research Instite

• YAMANISHI Toshihiko

  Tritium Engineering Laboratory, Japan Atomic Energy Research Instite

• NISHI Masataka

  Tritium Engineering Laboratory, Japan Atomic Energy Research Instite

• Nishi Masataka

  Tritium Engineering Laboratory Department Of Fusion Engineering Research Japan Atomic Energy Researc

• Isobe Kanetsugu

  Tritium Engineering Laboratory Japan Atomic Energy Research Institute

• Nishi M

  Japan Atomic Energy Res. Inst. Ibaraki

• NAKAMURA Hirofumi

  Tritium Engineering Laboratory, Japan Atomic Energy Research Institute

• WILLMS R.

  Tritium Systems Test Assembly, Los Alamos National Laboratory

• Willms R.

  Tritium Systems Test Assembly Los Alamos National Laboratory

• Yamanishi T

  Tritium Engineering Laboratory Japan Atomic Energy Research Institute

• Yamanishi Toshihiko

  Tritium Engineering Laboratory Japan Atomic Energy Research Institute

• Nakamura Hirofumi

  Tritium Engineering Laboratory Japan Atomic Energy Research Institute

関連論文

• 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)
• 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
• 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
• Simulation of Tritium Behavior after Intended Tritium Release in Ventilated Room
• 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
• Durability of Irradiated Polymers in Solid-Polymer-Electrolyte Water Electrolyzer
• Tritium Decontamination from Co-deposited Layer on Tungsten Substrate by Ultra Violet Lamp and Laser
• Control Characteristics of Cryogenic Distillation Column with a Feedback Stream for Fusion Reactor
• Seasonal changes of tritium gas oxidizing airborne bacteria in TPL of Japan Atomic Energy Research Institute
• Application of Pressure Swing Adsorption to Water Detritiation Process
• Numerical Estimation Method of the Hydrogen Isotope Inventory in the Hydrogen Isotope Separation System for Fusion Reactor
• Adsorption Isotherms of Hydrogen Isotopes on Molecular Sieves 5A at Low Temperature
• ANALYSIS OF CHARACTERISTICS OF CRYOGENIC DISTILLATION COLUMN IN SEPARATION OF HYDROGEN ISOTOPES
• Room-Temperature Reactor Packed with Hydrophobic Catalysts for the Oxidation of Hydrogen Isotopes Released in a Nuclear Facility
• Removal of Co-deposited Layers by Excimer Lasers
• 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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