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R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA

H. Tanigawa, T. Hoshino, Y. Kawamura, M. Nakamichi, K. Ochiai, M. Akiba, M. Ando, M. Enoeda, K. Ezato, K. Hayashi2009年被引用 23Nuclear FusionIF 3出版社

At JAEA, a test blanket module (TBM) with a water-cooled solid breeder is being developed. This paper presents recent achievements of research activities for the TBM, particularly addressing the pebble bed of the tritium breeder materials and tritium behaviour. For the breeder material, the chemical stability of Li2TiO3 was improved using Li2O additives. To analyse the pebble bed behaviour, thermomechanical properties of the Li2TiO3 pebble bed were assessed experimentally. To verify the pebble bed's nuclear properties, the activation foil method was proposed and a preliminary experiment was conducted. To reduce the tritium permeation, the chemical densified coating method was developed and the coating was attached to F82H steel. For tritium behaviour, the tritium recovery system was modified in consideration of the design change of the TBM.

日本語訳

JAEAでは、水冷却固体増殖ブランケット試験モジュール(TBM)の開発が進められている。本論文では、TBMに関する研究活動の最近の成果、特にトリチウム増殖材料のペブルベッドとトリチウム挙動について述べる。増殖材料については、Li2O添加剤を用いてLi2TiO3の化学的安定性を改善した。ペブルベッド挙動を解析するため、Li2TiO3ペブルベッドの熱力学的機械的特性を実験的に評価した。ペブルベッドの核的特性を検証するため、放射化箔法を提案し、予備実験を実施した。トリチウム透過を低減するため、化学的緻密化コーティング法を開発し、F82H鋼にコーティングを施した。トリチウム挙動については、TBMの設計変更を考慮してトリチウム回収システムを改良した。

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Test blanket moduleBlanket modulePebble bedLithium titanate
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