Study of evaporating the irradiated graphite in equilibrium low-temperature plasma
| Parent link: | Thermophysics and Aeromechanics Vol. 25, iss. 1.— 2018.— [P. 109–117] |
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| Співавтор: | |
| Інші автори: | , , , |
| 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
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| 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 |