Modeling of Processing of Irradiated Graphite Contained Fission and Neutron-Activation Products by Noble Gas Flow; AIP Conference Proceedings; Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018)
| Parent link: | AIP Conference Proceedings Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018).— 2019.— [020004, 8 p.] |
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| Korporativní autor: | |
| Další autoři: | , , , , |
| Shrnutí: | Title screen The paper discusses questions dedicated accumulation of graphite radioactive waste generated during commissioning of uranium-graphite nuclear reactor. Authors determine character of contamination of irradiated graphite by different radionuclides (especially 1{37}Cs, {60}Co, {90}Sr) using autoradiographic methods and by means of electron microscope (scanning electron microscope - analysis). It has been obtained images of polished section of irradiated graphite in back-scattered electrons. Authors suggest the method of thermal decontamination of irradiated graphite surface by noble gas flow for the purpose of potential hazard reduction of graphite radioactive waste. The developed mathematical model of thermal decontamination of irradiated graphite subject to Wigner energy release under radiation defect annealing has been demonstrated in paper. The article represents laws reflecting dependence of recession velocity of radioactive contamination of graphite radioactive waste and different parameters of process subject to Wigner energy release. Режим доступа: по договору с организацией-держателем ресурса |
| Jazyk: | angličtina |
| Vydáno: |
2019
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| Témata: | |
| On-line přístup: | https://doi.org/10.1063/1.5099596 |
| Médium: | MixedMaterials Elektronický zdroj Kapitola |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=660277 |