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The effect of 14 MeV neutron irradiation on tritium recovery from lithium oxide

Hirotake Moriyama, Jun Oishi, Takayuki Terai, Kazutaka Kawamura1989年Fusion Engineering and DesignIF 1.7出版社

Post-irradiation experiments were performed to study the effect of 14 MeV neutron irradiation on the recovery of tritium from sintered lithium oxide. The chemical state distribution of tritium produced in the lithium oxide was found to depend on the neutron fluence because of the influence of radiation defects. When the lithium oxide was heated with a helium sweep gas, tritium was recovered mainly as HTO and its recovery was controlled by bulk diffusion of tritium in the T+ state except in an early period of recovery. The diffusion coefficient was expressed as D = 4.4 exp [−143 (kJ mol−1)/RT] cm2 s−1. When hydrogen was added to the sweep gas, on the other hand, a considerable amount of tritium was recovered as HT. The HT recovery was analyzed with first-order kinetics using the activation energy of 137 kJ mol−1. The reactions of tritium with F+ centers may be responsible for the observed behaviour.

日本語訳

照射後実験を実施し、14 MeV中性子照射が焼結酸化リチウムからのトリチウム回収に及ぼす影響を調べた。酸化リチウム中で生成したトリチウムの化学状態の分布は、照射欠陥の影響により、中性子フルエンスに依存することが見出された。ヘリウムスイープガスを用いて酸化リチウムを加熱した場合、トリチウムは主にHTOとして回収され、その回収は初期の期間を除いて、T+状態のトリチウムのバルク拡散によって支配された。拡散係数はD = 4.4 exp [−143 (kJ mol−1)/RT] cm2 s−1と表された。一方、スイープガスに水素を添加した場合、かなりの量のトリチウムがHTとして回収された。HTの回収は、活性化エネルギー137 kJ mol−1を用いた一次反応速度論によって解析された。トリチウムとF+中心との反応が、観測された挙動の原因である可能性がある。

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TritiumLithiumNeutron irradiationTritium recovery
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