Fast reactor BREST-300
| Parent link: | Методология проектирования молодежного научно-инновационного пространства как основа подготовки современного инженера.— 2014.— [С. 61-64] |
|---|---|
| Main Author: | |
| Corporate Author: | |
| Other Authors: | , , , |
| Summary: | Заглавие с экрана 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. |
| Language: | English |
| Published: |
2014
|
| Series: | Nuclear technologies as integral part of engineering science in the modern world |
| Subjects: | |
| Online Access: | http://earchive.tpu.ru/handle/11683/64976 http://www.lib.tpu.ru/fulltext/c/2014/C07/012.pdf |
| Format: | Electronic Book Chapter |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=607912 |