Study of tritium and helium generation and release from lead-lithium eutectics Li15.7Pb under neutron irradiation

書誌詳細
Parent link:Fusion Engineering and Design
Vol. 146.— 2019.— [P. 1317-1320]
団体著者: Национальный исследовательский Томский политехнический университет Физико-технический институт Лаборатория № 31 ядерного реактора
その他の著者: Kulsartov T. V. Timur, Zaurbekova Zh. A. Zhanna Askhatovna, Tazhibaeva I. L. Irina Lashkarovna, Ponkratov Yu. V. Yury Valentinovich, Gnyrya V. S. Vyacheslav Sergeevich, Kizane G. Gunta, Nesterov E. A. Evgeny Alexandrovich, Varlamova N. V. Natalya Valeryevna
要約:Title screen
This paper describes the experiments on study of tritium and helium generation and release processes from lead-lithium eutectics Li15.7Pb. The irradiation was performed at the IVG.1M research reactor at 6 MW of thermal power. The irradiation temperature increased step by step from 225 to 550 °C. A qualitative assessment of the experimental results showed that as the temperature rises above 390 °C, the tritium flux from the sample consisting of T2 and HT molecules decreases. It was concluded that the observed effect is similar to the previously observed one for lead-lithium eutectics with Li17Pb83 composition.
Режим доступа: по договору с организацией-держателем ресурса
出版事項: 2019
主題:
オンライン・アクセス:https://doi.org/10.1016/j.fusengdes.2020.112167
フォーマット: 電子媒体 図書の章
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=664136

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