Effect of fuel nuclide composition on the fuel lifetime of reactor KLT-40S; Nuclear Engineering and Design; Vol. 360
| Parent link: | Nuclear Engineering and Design Vol. 360.— 2020.— [110524, 7 p.] |
|---|---|
| مؤلف مشترك: | |
| مؤلفون آخرون: | , , , , |
| الملخص: | Title screen Fuel lifetime is a crucial parameter for small reactors used as the main part of floating power plants. Such plants have the potential to solve energy supply problems of remote regions. This article explains the methodology used to determine the effective multiplication factors and breeding ratios for reactor KLT-40S (Korpusnoi Ledokolnogo Tipa; [Shell-Type Reactor of Icebreaker Kind]) under operating conditions. The following parameters are shown to affect fuel lifetime: - effective neutron multiplication factor; - breeding ratio of nuclear fuel; - and fuel element diameter or volume of charged fuel. An increase in these parameters extends fuel lifetime. Four different fuel compositions, namely, (U238 + U235)O2, (U238 + Pu239)O2, (Th232 + U235)O2, and (Th232 + U233)O2, were examined to calculate possible fuel lifetime. The dependence of lifetime on the fuel rod diameter was also determined.The study shows that Th-U fuel cycle offers great lifetime advantages over the conventional U–Pu fuel cycle. Switching the fuel composition to (Th232 + U233)O2 can prolong fuel lifetime by 75%. Режим доступа: по договору с организацией-держателем ресурса |
| اللغة: | الإنجليزية |
| منشور في: |
2020
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| الموضوعات: | |
| الوصول للمادة أونلاين: | https://doi.org/10.1016/j.nucengdes.2020.110524 |
| التنسيق: | MixedMaterials الكتروني فصل الكتاب |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=661767 |
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| 200 | 1 | |a Effect of fuel nuclide composition on the fuel lifetime of reactor KLT-40S |f S. V. Belyavsky, V. N. Nesterov, R. A. Laas [et al.] | |
| 203 | |a Text |c electronic | ||
| 300 | |a Title screen | ||
| 320 | |a [References: 24 tit.] | ||
| 330 | |a Fuel lifetime is a crucial parameter for small reactors used as the main part of floating power plants. Such plants have the potential to solve energy supply problems of remote regions. This article explains the methodology used to determine the effective multiplication factors and breeding ratios for reactor KLT-40S (Korpusnoi Ledokolnogo Tipa; [Shell-Type Reactor of Icebreaker Kind]) under operating conditions. The following parameters are shown to affect fuel lifetime: - effective neutron multiplication factor; - breeding ratio of nuclear fuel; - and fuel element diameter or volume of charged fuel. An increase in these parameters extends fuel lifetime. Four different fuel compositions, namely, (U238 + U235)O2, (U238 + Pu239)O2, (Th232 + U235)O2, and (Th232 + U233)O2, were examined to calculate possible fuel lifetime. The dependence of lifetime on the fuel rod diameter was also determined.The study shows that Th-U fuel cycle offers great lifetime advantages over the conventional U–Pu fuel cycle. Switching the fuel composition to (Th232 + U233)O2 can prolong fuel lifetime by 75%. | ||
| 333 | |a Режим доступа: по договору с организацией-держателем ресурса | ||
| 461 | |t Nuclear Engineering and Design | ||
| 463 | |t Vol. 360 |v [110524, 7 p.] |d 2020 | ||
| 610 | 1 | |a электронный ресурс | |
| 610 | 1 | |a труды учёных ТПУ | |
| 610 | 1 | |a reactor KLT-40S | |
| 610 | 1 | |a effective multiplication factor | |
| 610 | 1 | |a breeding ratio | |
| 610 | 1 | |a thorium-uranium fuel cycle | |
| 610 | 1 | |a uranium–plutonium fuel cycle | |
| 610 | 1 | |a fuel lifetime | |
| 610 | 1 | |a топливо | |
| 610 | 1 | |a реакторы | |
| 610 | 1 | |a торий-урановый цикл | |
| 610 | 1 | |a уран-плутониевый цикл | |
| 701 | 1 | |a Belyavsky |b S. V. |g Sergey Vladimirovich | |
| 701 | 1 | |a Nesterov |b V. N. |c specialist in the field of nuclear energy |c associate Professor of Tomsk Polytechnic University, candidate of technical Sciences |f 1977- |g Vladimir Nikolaevich |3 (RuTPU)RU\TPU\pers\35579 |9 18749 | |
| 701 | 1 | |a Laas |b R. A. |c Physicist |c Assistant of the Department of Tomsk Polytechnic University |f 1991- |g Roman Aleksandrovich |3 (RuTPU)RU\TPU\pers\35139 |9 18414 | |
| 701 | 1 | |a Godovykh |b A. V. |g Aleksey Valerjevich | |
| 701 | 1 | |a Bulakh |b O. I. |g Olga Igorevna | |
| 712 | 0 | 2 | |a Национальный исследовательский Томский политехнический университет |b Инженерная школа ядерных технологий |b Отделение ядерно-топливного цикла |3 (RuTPU)RU\TPU\col\23554 |
| 801 | 2 | |a RU |b 63413507 |c 20200214 |g RCR | |
| 850 | |a 63413507 | ||
| 856 | 4 | |u https://doi.org/10.1016/j.nucengdes.2020.110524 | |
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