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http://earchive.tpu.ru/handle/11683/64976| Title: | Fast reactor BREST-300 |
| Authors: | Novoselov, A. E. Stolov, E. V. Nefedov, V. S. |
| metadata.dc.contributor.advisor: | Liventsova, Nina Vladimirovna Kabrysheva, Oksana Pavlovna |
| Keywords: | быстрые реакторы; Брест-300; атомная энергетика; быстрые нейтроны; тепловая энергия |
| Issue Date: | 2014 |
| Publisher: | Томский политехнический университет |
| Citation: | Novoselov A. E. Fast reactor BREST-300 / A. E. Novoselov, E. V. Stolov, V. S. Nefedov ; Sci. adv. N. V. Liventsova, O. P. Kabrysheva // Методология проектирования молодежного научно-инновационного пространства как основа подготовки современного инженера : сборник научных трудов Международной молодежной научной школы, г. Томск, 2 - 4 апреля 2014 г. — Томск : Изд-во ТПУ, 2014. — [С. 61-64]. |
| Abstract: | This paper describes the nearest future of nuclear power engineering in terms of fast reactor - BREST-300. The article shows its design, characteristics and benefits of fast reactors. Even modern reactors with slow neutrons have high energy rates, but there are some problems such as rarity of Uranium -235 and large amounts of waste. The Russian development of BREST-300 is able to solve some of the problems. Key words: BREST-300, fast reactor(FR), loop, fuel assembly (FA), closed nuclear fuel cycle (CFC), thermal power, electric power, fuel lifetime. |
| URI: | http://earchive.tpu.ru/handle/11683/64976 |
| Appears in Collections: | Материалы конференций |
Files in This Item:
| File | Description | Size | Format | |
|---|---|---|---|---|
| conference_tpu-2014-C07_p61-64.pdf | 175,61 kB | Adobe PDF | View/Open |
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