FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Zr2Fe and Zr(Mn0.5Fe0.5)2 particle beds for tritium purification and impurity removal in a fusion fuel cycle

Satoshi Fukada, Yoshiki Toyoshima, Masabumi Nishikawa2000年Fusion Engineering and DesignIF 1.7出版社

AbstractParticle beds of Zr(Mn0.5Fe0.5)2 and Zr2Fe are studied for impurity decomposition and hydrogen isotope recovery in a fuel cycle of a nuclear fusion reactor. The Zr(Mn0.5Fe0.5)2 particle bed can decompose methane into hydrogen and a zirconium carbide at temperatures higher than 650°C and water vapor into hydrogen and oxides at temperatures higher than 350°C. Each of the rate constants is correlated to the Arrhenius equation. The Zr2Fe particle bed pretreated with a 6N NaOH solution can recover H2 or D2 in carrier gas down to less than 1 ppm at room temperature.

日本語訳

Zr(Mn0.5Fe0.5)2およびZr2Fe粒子充填層が、核融合炉燃料サイクルにおける不純物分解と水素同位体回収のために研究されている。Zr(Mn0.5Fe0.5)2粒子充填層は、650°C以上の温度でメタンを水素と炭化ジルコニウムに分解し、350°C以上の温度で水蒸気を水素と酸化物に分解することができる。各速度定数はアレニウス式に相関付けられている。6N NaOH溶液で前処理したZr2Fe粒子充填層は、室温でキャリアガス中のH2またはD2を1ppm未満まで回収することができる。

wiki

TritiumImpurity
この論文にはまだAI要約がありません。

関連論文

Study of the high efficiency of ZrNi alloys for tritium gettering properties

2001Fusion Engineering and Design

Absorption breakthrough of hydrogen isotopes and desorption in a zirconium-vanadium particle bed

1989Fusion Engineering and Design

Recovery of low-concentration hydrogen from different gas streams with Zr2Fe particle beds

1997Fusion Engineering and Design

Development of tritium processing material — A U-Zr alloy as a promising tritium storage material

1988Fusion Engineering and Design

Effects of alpha particles on the CTEM driven zonal flow in deuterium–tritium tokamak plasmas

2022Nuclear Fusion

On the thermal stability of the zirconium/cobalt–hydrogen system

2000Fusion Engineering and Design

Development of zirconium-cobalt beds for recovery, storage and supply of tritium

1989Fusion Engineering and Design

Progress of fusion fuel processing system development at the Japan Atomic Energy Research Institute

2000Fusion Engineering and Design

Study on T production using high-temperature gas-cooled reactor for DEMO fusion reactor − H absorption properties of Zr sphere with Ni coating

2025Fusion Engineering and Design

Experimental investigation of tritium release behavior from neutron irradiated LiAlO2 with Zr for tritium production in a high-temperature gas-cooled reactor

2024Fusion Engineering and Design