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Management of tritium-contaminated wastes at the ethel facility: Future trends for routine management practices and experimental research activities

F. Mannone, H. Dworschak1987年Fusion Engineering and DesignIF 1.7出版社

In the frame of JRC's 1984–1987 Fusion Technology Programme and with the aim of contributing to tritium R&D for NET, the Commission of the European Communities decided in July 1985 to construct the European Tritium Handling Experimental Laboratory (ETHEL) on the site of the Ispra Establishment. ETHEL is a facility designed to handle a maximum inventory of 100 g tritium. Its detailed design study was started in January 1987 and its commissioning is foreseen for end 1989 - beginning 1990. Being well aware of the lack of an efficient, economic and safe technology in the field of tritiated waste management, extensive laboratory research on tritiated waste treatment, conditioning and containment inside multibarrier systems, has been proposed by the research staff of the Ispra Establishment as one of the experimental activities to be performed at ETHEL. Current practices to be applied for routine management of tritiated waste generated during the normal ETHEL operations, as well as objectives of the experimental research that the JRC staff specifically intend to perform in the field of tritiated waste management strategy, are described.

日本語訳

抄録: 欧州トリチウム取扱実験室(ETHEL)の枠組みにおいて、欧州共同体合同研究センター(JRC)イスプラ研究所の研究スタッフは、トリチウム廃棄物の管理戦略に関する実験研究を実施することを提案している。本論文では、通常のETHEL運転中に発生するトリチウム廃棄物の日常的な管理に適用される現在の慣行と、JRCスタッフがトリチウム廃棄物管理戦略の分野で具体的に実施することを意図している実験研究の目的について述べる。 ETHELは、最大100gのトリチウムインベントリを収容するように設計された施設である。その詳細設計研究は1987年1月に開始され、試運転は1989年末から1990年初めにかけて予定されている。多重バリアシステム内でのトリチウム廃棄物の処理、調整、封じ込めに関する効率的かつ安全な技術が不足していることを認識し、イスプラ研究所の研究スタッフは、ETHELで実施すべき実験活動の一つとして、トリチウム廃棄物の処理、調整、封じ込めに関する広範な実験室研究を提案している。

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