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Development of tritium cleanup system for LHD

Yoichi Sakuma, Takao Kawano, Mamoru Shibuya, Toshiki Kabutomori2000年Fusion Engineering and DesignIF 1.7出版社

AbstractEnergy is vital for humans and we have been consuming a large amount of fossil fuel especially from the beginning of the industrial revolution. Nowadays its huge consumption has however come to threaten our life and we have to prepare nonfossil fuels, for instance solar energy, biomass energy, nuclear energy and so on. Fusion energy is an unlimited resource and one of the strongest candidates of the future energy source. At the National Institute for Fusion Science (referred to as ‘NIFS’ hereafter), we have constructed a new fusion experimental device called large helical device (referred to as ‘LHD’ hereafter) in 1998. The device will generate a small amount of tritium, as a fusion product. In order to remove it from the exhaust gas, we have designed a tritium cleanup system based on a new concept. This system is mainly composed of a palladium permeater, a decomposer and hydrogen absorbing alloys. It may perfectly recover the tritium from exhaust gas without oxidizing it. This system is applicable for the future needs at fusion power plants. In order to remove tritium discharged from fusion experimental facilities, it is usual to employ a system by which tritiated constituents, in various chemical forms, are entirely converted to a form of water vapor by catalytic oxidation. The water vapor containing tritiated form is then absorbed by molecular sieve (referred to as ‘wet system’ hereafter). However, in the case of LHD, it is not rational to deliberately convert the discharged tritium into the water vapor, because the tritium discharged from LHD is almost in a form of hydrogen molecules. Moreover, the tritium in the form of water vapor affects the human body 18 000 times stronger than that of hydrogen molecules. In accordance with these view points, we have developed another type of tritium cleanup system based on a new concept, in which hydrogen molecules including tritiated ones (HT, DT and T2) found in the exhaust gas of LHD are directly fixed to hydrogen absorbing alloys. Other impurities such as methane and water vapor, parts of which are tritiated, will be decomposed into each elemental form by the decomposition process and hydrogen molecules, including tritiated constituents from the decomposition (referred to as ‘dry system’ hereafter).

日本語訳

エネルギーは人間にとって不可欠であり、我々は産業革命の開始以来、特に大量の化石燃料を消費してきた。今日、その大量消費は我々の生活を脅かすまでに至っており、太陽エネルギー、バイオマスエネルギー、原子力エネルギーなどの非化石燃料を準備しなければならない。核融合エネルギーは無尽蔵のエネルギーであり、未来のエネルギー源の有力な候補の一つである。核融合科学研究所(以下NIFSと略す)では、1998年に大型ヘリカル装置(以下LHDと略す)という新しい核融合実験装置を建設した。この装置は少量のトリチウムを生成するが、核融合生成物として排気ガス中に含まれる。排気ガスからトリチウムを除去するため、我々は新しい概念に基づくトリチウム浄化システムを設計した。このシステムは主にパラジウム透過膜、分解装置、水素吸蔵合金から構成される。従来の核融合実験施設から排出されるトリチウムを除去する方法は、通常、触媒酸化によりトリチウムを含む様々な化学形態のトリチウム化合物をすべて水蒸気に変換し、その後モレキュラーシーブスで吸着するというものである(以下「湿式法」と略す)。しかし、LHDの場合、排出されるトリチウムはほとんどが水素分子の形であるため、わざわざ水蒸気に変換するのは合理的ではない。さらに、水蒸気の形のトリチウムは水素分子の形のトリチウムよりも人体への影響が約18000倍大きい。これらの観点から、我々は新しい概念に基づく別のタイプのトリチウム浄化システムを開発した。このシステムでは、LHDの排気ガス中に含まれるトリチウム化水素分子(HT、DT、T2)を直接水素吸蔵合金に固定する。トリチウムを含むメタンや水蒸気などの不純物は、分解装置で各元素に分解され、生成した水素分子(トリチウムを含む)も吸蔵される(以下「乾式法」と略す)。

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