Research of impact of kind resuperheat and structure of system regenerative feed water to thermodynamic efficiency of cycle with steamcoolant reactor
| Parent link: | MATEC Web of Conferences Vol. 141 : Smart Grids 2017.— 2017.— [01028, 5 p.] |
|---|---|
| Corporate Authors: | , |
| Outros Autores: | , , , , |
| Resumo: | Title screen The first key problems of modern nuclear reactors are inability of closed nuclear cycle, problems with spent nuclear fuel, poor effectiveness of nuclear fuel and heat-exchange equipment usage. Dealing with problems consists in usage of fast-neutron reactors with steam coolant. Scientific men analyzed neutron-physical processes in steamcooled fast reactor and consulted that creation of the reactor is viable. In consequence of low steam activation a single-loop steam cycle may be create. The cycle is easy and fool-proof. Core thermomechanical equipment has mastered and has relatively low metal content. Results of calculation are showing that nuclear unit with steam-coolant fast neutron reactor is more efficient than widely used unit with reactor VVER. Usage of simple scheme with four regenerative feedwater heaters the absolute efficiency ratio is more than 43%. |
| Idioma: | inglês |
| Publicado em: |
2017
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| Assuntos: | |
| Acesso em linha: | https://doi.org/10.1051/matecconf/201714101028 http://earchive.tpu.ru/handle/11683/46015 |
| Formato: | Recurso Electrónico Capítulo de Livro |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=657284 |
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| 200 | 1 | |a Research of impact of kind resuperheat and structure of system regenerative feed water to thermodynamic efficiency of cycle with steamcoolant reactor |f S. Maykova [et al.] | |
| 203 | |a Text |c electronic | ||
| 300 | |a Title screen | ||
| 320 | |a [References: 7 tit.] | ||
| 330 | |a The first key problems of modern nuclear reactors are inability of closed nuclear cycle, problems with spent nuclear fuel, poor effectiveness of nuclear fuel and heat-exchange equipment usage. Dealing with problems consists in usage of fast-neutron reactors with steam coolant. Scientific men analyzed neutron-physical processes in steamcooled fast reactor and consulted that creation of the reactor is viable. In consequence of low steam activation a single-loop steam cycle may be create. The cycle is easy and fool-proof. Core thermomechanical equipment has mastered and has relatively low metal content. Results of calculation are showing that nuclear unit with steam-coolant fast neutron reactor is more efficient than widely used unit with reactor VVER. Usage of simple scheme with four regenerative feedwater heaters the absolute efficiency ratio is more than 43%. | ||
| 461 | 0 | |0 (RuTPU)RU\TPU\network\4526 |t MATEC Web of Conferences | |
| 463 | 0 | |0 (RuTPU)RU\TPU\network\23742 |t Vol. 141 : Smart Grids 2017 |o The Fifth International Youth Forum, October 9-13, 2017, Tomsk, Russia |o [proceedings] |f National Research Tomsk Polytechnic University (TPU) ; eds. A. A. Kozyreva, A. O. Zhdanova, G. V. Kuznetsov |v [01028, 5 p.] |d 2017 | |
| 610 | 1 | |a электронный ресурс | |
| 610 | 1 | |a труды учёных ТПУ | |
| 610 | 1 | |a рекуперация | |
| 610 | 1 | |a тепло | |
| 610 | 1 | |a питательная вода | |
| 610 | 1 | |a термодинамическая эффективность | |
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| 610 | 1 | |a ядерное топливо | |
| 610 | 1 | |a отработанное топливо | |
| 610 | 1 | |a теплообменное оборудование | |
| 610 | 1 | |a реакторы на быстрых нейтронах | |
| 701 | 1 | |a Maykova |b S. |g Svetlana | |
| 701 | 1 | |a Borisov |b V. |g Vassily | |
| 701 | 1 | |a Antonova |b A. M. |c specialist in the field of power engineering |c Associate Professor of Tomsk Polytechnic University, Candidate of technical sciences |f 1952- |g Aleksandra Mikhailovna |y Tomsk |3 (RuTPU)RU\TPU\pers\35870 |9 19013 | |
| 701 | 1 | |a Vorobiev |b A. V. |c specialist in the field of power engineering |c Associate Professor of Tomsk Polytechnic University, Candidate of technical sciences |f 1949- |g Aleksandr Vladimirovich |3 (RuTPU)RU\TPU\pers\35869 |9 19012 | |
| 701 | 1 | |a Abramovskikh |b A. A. |c specialist in the field of power engineering |c senior lecturer of Tomsk Polytechnic University |f 1982- |g Aleksey Andreevich |3 (RuTPU)RU\TPU\pers\35671 | |
| 712 | 0 | 2 | |a Национальный исследовательский Томский политехнический университет (ТПУ) |b Инженерная школа энергетики (ИШЭ) |b Научно-образовательный центр И. Н. Бутакова (НОЦ И. Н. Бутакова) |3 (RuTPU)RU\TPU\col\23504 |
| 712 | 0 | 2 | |a Национальный исследовательский Томский политехнический университет (ТПУ) |b Энергетический институт (ЭНИН) |b Кафедра атомных и тепловых электростанций (АТЭС) |3 (RuTPU)RU\TPU\col\18683 |
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