Study of evaporating the irradiated graphite in equilibrium low-temperature plasma

Бібліографічні деталі
Parent link:Thermophysics and Aeromechanics
Vol. 25, iss. 1.— 2018.— [P. 109–117]
Співавтор: Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение ядерно-топливного цикла
Інші автори: Bespala E. V. Evgeniy (Evgeny) Vladimirovich, Novoselov I. Yu. Ivan Yurievich, Pavlyuk (Pavliuk) A. O. Aleksander Olegovich, Kotlyarevsky S. G. Sergey Gennadjevich
Резюме:Title screen
The paper describes a problem of accumulation of irradiated graphite due to operation of uranium-graphite nuclear reactors. The main noncarbon contaminants that contribute to the overall activity of graphite elements are iso-topes 137Cs, 60Co, 90Sr, 36Cl, and 3H. A method was developed for processing of irradiated graphite ensuring the volu-metric decontamination of samples. The calculation results are presented for equilibrium composition of plasma-chemical reactions in systems “irradiated graphite-argon” and “irradiated graphite-helium” for a wide range of tem-peratures. The paper describes a developed mathematical model for the process of purification of a porous graphite surface treated by equilibrium low-temperature plasma. The simulation results are presented for the rate of sublimation of radioactive contaminants as a function of plasma temperature and plasma flow velocity when different plasma-forming gases are used. The extraction coefficient for the contaminant 137Cs from the outer side of graphite pores was calculated. The calculations demonstrated the advantages of using a lighter plasma forming gas, i.e., helium.
Режим доступа: по договору с организацией-держателем ресурса
Опубліковано: 2018
Предмети:
Онлайн доступ:https://doi.org/10.1134/S0869864318010109
Формат: Електронний ресурс Частина з книги
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=667166