Analysis of reactor experiments to study the transfer processes of generated tritium in lithium CPS (capillary-porous system); International Journal of Hydrogen Energy; Vol. 47, iss. 11

Bibliografski detalji
Parent link:International Journal of Hydrogen Energy
Vol. 47, iss. 11.— 2022.— [P. 7368-7378]
Autor kompanije: Национальный исследовательский Томский политехнический университет Физико-технический институт Лаборатория № 31 ядерного реактора
Daljnji autori: Askerbekov S. K. Saulet Kanybekuly, Kenzhina I. Е. Inesh, Kulsartov T. V. Timur, Chikhray E. V. Evgeny Vasiljevich, Tazhibaeva I. L. Irina Lashkarovna, Ponkratov Yu. V. Yury Valentinovich, Gordienko Yu. N. Yury Nikolaevich, Zaurbekova Zh. A. Zhanna Askhatovna, Gabdullin M. T. Maratbek Tulebergenovich, Kadyrzhanov K. K. Kayrat Kamalovich, Nesterov E. A. Evgeny Alexandrovich
Sažetak:Title screen
To date, there have been many studies on the possibility of using lithium CPS as a plasma-facing material in fusion reactors. For use such liquid-lithium systems in fusion reactors, it is necessary to determine the interaction parameters of the surface facing the plasma with the working gases under conditions simulating the real operation of the facility, i.e. under conditions of neutron and gamma radiation. Therefore, this paper is devoted to the study of the processes of hydrogen isotopes interaction with lithium CPS under reactor irradiation. The experiments presented in work were carried out at the IVG1.M research reactor by using dynamic sorption method with the presence of deuterium under the lithium CPS sample. The results of reactor experiments simulation, in particular, the distribution of tritium concentration in lithium volume and traps, and the flows of tritium released through the inner surface of the CPS into the experimental chamber at different temperatures are presented. Based on the simulation results, the following interaction parameters of tritium with lithium were determined: temperature dependences of tritium capture constant by lithium and the dissociation constant of LiT. The obtained model can be applied for analysis of tritium generation and release from different lithium-containing materials used as a filling of CPS structure (for example, lithium and tin-lithium eutectics).
Режим доступа: по договору с организацией-держателем ресурса
Jezik:engleski
Izdano: 2022
Teme:
Online pristup:https://doi.org/10.1016/j.ijhydene.2021.03.163
Format: Elektronički Poglavlje knjige
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=667035

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200 1 |a Analysis of reactor experiments to study the transfer processes of generated tritium in lithium CPS (capillary-porous system)  |f S. K. Askerbekov, I. Е. Kenzhina, T. V. Kulsartov [et al.] 
203 |a Text  |c electronic 
300 |a Title screen 
320 |a [References: 32 tit.] 
330 |a To date, there have been many studies on the possibility of using lithium CPS as a plasma-facing material in fusion reactors. For use such liquid-lithium systems in fusion reactors, it is necessary to determine the interaction parameters of the surface facing the plasma with the working gases under conditions simulating the real operation of the facility, i.e. under conditions of neutron and gamma radiation. Therefore, this paper is devoted to the study of the processes of hydrogen isotopes interaction with lithium CPS under reactor irradiation. The experiments presented in work were carried out at the IVG1.M research reactor by using dynamic sorption method with the presence of deuterium under the lithium CPS sample. The results of reactor experiments simulation, in particular, the distribution of tritium concentration in lithium volume and traps, and the flows of tritium released through the inner surface of the CPS into the experimental chamber at different temperatures are presented. Based on the simulation results, the following interaction parameters of tritium with lithium were determined: temperature dependences of tritium capture constant by lithium and the dissociation constant of LiT. The obtained model can be applied for analysis of tritium generation and release from different lithium-containing materials used as a filling of CPS structure (for example, lithium and tin-lithium eutectics). 
333 |a Режим доступа: по договору с организацией-держателем ресурса 
461 |t International Journal of Hydrogen Energy 
463 |t Vol. 47, iss. 11  |v [P. 7368-7378]  |d 2022 
610 1 |a электронный ресурс 
610 1 |a труды учёных ТПУ 
610 1 |a lithium CPS 
610 1 |a reactor experiments 
610 1 |a tritium 
610 1 |a deuterium 
610 1 |a lithium 
610 1 |a перенос 
610 1 |a тритий 
610 1 |a капиллярно-пористые материалы 
610 1 |a плазма 
610 1 |a литий 
610 1 |a термоядерные реакторы 
701 1 |a Askerbekov  |b S. K.  |g Saulet Kanybekuly 
701 1 |a Kenzhina  |b I. Е.  |g Inesh 
701 1 |a Kulsartov  |b T. V.  |g Timur 
701 1 |a Chikhray  |b E. V.  |g Evgeny Vasiljevich 
701 1 |a Tazhibaeva  |b I. L.  |g Irina Lashkarovna 
701 1 |a Ponkratov  |b Yu. V.  |g Yury Valentinovich 
701 1 |a Gordienko  |b Yu. N.  |g Yury Nikolaevich 
701 1 |a Zaurbekova  |b Zh. A.  |g Zhanna Askhatovna 
701 1 |a Gabdullin  |b M. T.  |g Maratbek Tulebergenovich 
701 1 |a Kadyrzhanov  |b K. K.  |g Kayrat Kamalovich 
701 1 |a Nesterov  |b E. A.  |c Physicist, Specialist in the field of nuclear power engineering  |c Researcher of Tomsk Polytechnic University  |f 1976-  |g Evgeny Alexandrovich  |3 (RuTPU)RU\TPU\pers\32657  |9 16556 
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