Electrochemical treatment of irradiated nuclear graphite; Journal of Nuclear Materials; Vol. 526
| Parent link: | Journal of Nuclear Materials Vol. 526.— 2019.— [151759, 12 p.] |
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| Institution som forfatter: | |
| Andre forfattere: | , , , , , , |
| Summary: | 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 |
| Sprog: | engelsk |
| Udgivet: |
2019
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| Fag: | |
| Online adgang: | https://doi.org/10.1016/j.jnucmat.2019.151759 |
| Format: | Electronisk Book Chapter |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=660676 |
MARC
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| 200 | 1 | |a Electrochemical treatment of irradiated nuclear graphite |f E. V. Bespala [et al.] | |
| 203 | |a Text |c electronic | ||
| 300 | |a Title screen | ||
| 320 | |a [References: 56 tit.] | ||
| 330 | |a 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. | ||
| 333 | |a Режим доступа: по договору с организацией-держателем ресурса | ||
| 461 | |t Journal of Nuclear Materials | ||
| 463 | |t Vol. 526 |v [151759, 12 p.] |d 2019 | ||
| 610 | 1 | |a электронный ресурс | |
| 610 | 1 | |a труды учёных ТПУ | |
| 610 | 1 | |a irradiated graphite | |
| 610 | 1 | |a uranium-graphite reactor | |
| 610 | 1 | |a decontamination | |
| 610 | 1 | |a electrochemical treatment | |
| 610 | 1 | |a electrolyzer | |
| 610 | 1 | |a облученный графит | |
| 610 | 1 | |a уран-графитовые реакторы | |
| 610 | 1 | |a обеззараживание | |
| 610 | 1 | |a электрохимическая обработка | |
| 701 | 1 | |a Bespala |b E. V. |c engineer-physicist |c Associate Professor of Tomsk Polytechnic University, Candidate of Physical and Mathematical Sciences |f 1990- |g Evgeniy (Evgeny) Vladimirovich |9 88593 | |
| 701 | 1 | |a Antonenko |b M. V. |g Mikhail Viktorovich | |
| 701 | 1 | |a Chubreev |b D. O. |g Dmitry Olegovich | |
| 701 | 1 | |a Leonov |b A. V. |g Aleksey Vyacheslavovich | |
| 701 | 1 | |a Novoselov |b I. Yu. |c specialist in the field of nuclear physics |c Senior Lecturer of Tomsk Polytechnic University |f 1989- |g Ivan Yurievich |3 (RuTPU)RU\TPU\pers\34239 |9 17770 | |
| 701 | 1 | |a Pavlenko |b A. P. |g Anastasiya Pavlovna | |
| 701 | 1 | |a Kotov |b V. N. |g Vasily Nikolaevich | |
| 712 | 0 | 2 | |a Национальный исследовательский Томский политехнический университет |b Инженерная школа ядерных технологий |b Отделение ядерно-топливного цикла |3 (RuTPU)RU\TPU\col\23554 |
| 801 | 2 | |a RU |b 63413507 |c 20190926 |g RCR | |
| 856 | 4 | |u https://doi.org/10.1016/j.jnucmat.2019.151759 | |
| 942 | |c CF | ||