Оценка состояния графитовых материалов при облучении в ядерном реакторе
| Parent link: | Материалы и технологии новых поколений в современном материаловедении.— 2016.— [С. 79-84] |
|---|---|
| Main Author: | |
| Corporate Author: | |
| Other Authors: | , |
| Summary: | Заглавие с титульного экрана The paper provides guidance on the reprocessing of irradiated graphite in a lowtemperature plasma. The composition and properties of irradiated graphite of water- graphite reactors are considered. An assessment of the state of the graphitic material with long-term exposure in a nuclear reactor is given. These researches are necessary in the future to build a model of decontamination process for irradiated graphite. |
| Language: | Russian |
| Published: |
2016
|
| Series: | Проблемы прочности, пластичности и усталостной долговечности современных конструкционных материалов |
| Subjects: | |
| Online Access: | http://earchive.tpu.ru/handle/11683/30988 |
| Format: | Electronic Book Chapter |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=619066 |