Electrochemical treatment of irradiated nuclear graphite; Journal of Nuclear Materials; Vol. 526

Electrochemical treatment of irradiated nuclear graphite; Journal of Nuclear Materials; Vol. 526

Opis bibliograficzny
Parent link:	Journal of Nuclear Materials Vol. 526.— 2019.— [151759, 12 p.]
Korporacja:	Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение ядерно-топливного цикла
Kolejni autorzy:	Bespala E. V. Evgeniy (Evgeny) Vladimirovich, Antonenko M. V. Mikhail Viktorovich, Chubreev D. O. Dmitry Olegovich, Leonov A. V. Aleksey Vyacheslavovich, Novoselov I. Yu. Ivan Yurievich, Pavlenko A. P. Anastasiya Pavlovna, Kotov V. N. Vasily Nikolaevich
Streszczenie:	Title screen The paper is dedicated to the issues of accumulation of irradiated reactor graphite and possible options for handling it. There are described the advantages of the electrochemical method of decontamination of radioactive waste widely used in the nuclear industry. The use of this method to reduce the potential hazard of irradiated reactor graphite is proposed. The processes occurring during the removal of radioactive contamination from the surface of graphite radioactive waste are described. An experimental setup is presented to assess the possibility of using the method of electrochemical decontamination of irradiated graphite. The results of the determining the electrolyzer current-voltage curve and the dissolution rate of the electrodes made of irradiated graphite are presented. According to the results of experimental studies, data on the decontamination coefficients of irradiated graphite were obtained for various radionuclides (60Co, 137Cs, 154Eu, 152Eu) in HNO3, H2SO4, H2O, H2O2, HNO3 + KMnO4, H2SO4 + KMnO4 under various process modes. The evaluation of temperature fields inside the electrolyzer was carried out. The dependence of the removal efficiency of long-lived 14C radionuclide on the total mass loss of irradiated graphite was obtained. Режим доступа: по договору с организацией-держателем ресурса
Język:	angielski
Wydane:	2019
Hasła przedmiotowe:	электронный ресурс труды учёных ТПУ irradiated graphite uranium-graphite reactor decontamination electrochemical treatment electrolyzer облученный графит уран-графитовые реакторы обеззараживание электрохимическая обработка
Dostęp online:	https://doi.org/10.1016/j.jnucmat.2019.151759
Format:	Elektroniczne Rozdział
KOHA link:	https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=660676

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