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Inpile tritium release from ceramic breeder materials in TRIDEX experiments 1–6

W. Krug, H.G. Bays, H. Jünemann, W. Krauthausen, H. Werle1991年Fusion Engineering and DesignIF 1.7出版社

AbstractDependence of tritium release on purge gas chemistry has been studied in the temperature range 350–600°C for a variety of lithium orthosilicate and metazirconate samples (mainly 0.5 mm diameter pebbles) in the TRIDEX series of purged inpile tests. TRIDEX results were found to be in reasonable agreement with previous inpile experiments. Tritium release is remarkably improved by adding small percentages of hydrogen to the helium purge gas and/or by reducing the oxigen partial pressure of the helium purge gas. Similar tritium release behaviour of different charges of spheres prepared from molten orthosilicate demonstrates reproducibility of this fabrication route.

日本語訳

トリチウム放出のパージガス化学種への依存性が、多種多様なケイ酸リチウムおよびメタジルコン酸リチウム試料(主に直径0.5 mmの小球)について、TRIDEXシリーズのパージ式インパイル試験において350~600°Cの温度範囲で研究された。TRIDEXの結果は、これまでのインパイル実験と合理的に一致することが判明した。トリチウム放出は、ヘリウムパージガスへの水素の少量添加、および/またはヘリウムパージガスの酸素分圧の低減によって、著しく改善される。溶融オルソケイ酸塩から調製された異なるバッチの小球における同様のトリチウム放出挙動は、この製造経路の再現性を示している。

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