Study of tritium and helium generation and release from lead-lithium eutectics Li15.7Pb under neutron irradiation; Fusion Engineering and Design; Vol. 146

מידע ביבליוגרפי
Parent link:Fusion Engineering and Design
Vol. 146.— 2019.— [P. 1317-1320]
מחבר תאגידי: Национальный исследовательский Томский политехнический университет Физико-технический институт Лаборатория № 31 ядерного реактора
מחברים אחרים: 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
סיכום: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
שפה:אנגלית
יצא לאור: 2019
נושאים:
גישה מקוונת:https://doi.org/10.1016/j.fusengdes.2020.112167
פורמט: אלקטרוני Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=664136

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