Fuel lifetime extension for the KLT-40S small modular reactor by means of thorium-uranium fuel cycle
| Parent link: | Annals of Nuclear Energy.— .— Amsterdam: Elsevier Science Publishing Company Inc. Vol. 192.— 2023.— Article number 109982, 10 p. |
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| Інші автори: | , , , |
| Резюме: | Title screen This paper demonstrates the results of the Monte Carlo simulation conducted with MCU-PTR software for a small modular pressurized water reactor KLT-40S. Four dispersed fuel compositions, (U238 + U235)O2, (U238 + Pu239)O2, (Th232 + U235)O2, and (Th232 + U233)O2, were examined for fuel lifetime and fuel burnup calculations. The transition to the (Th232 + U233)O2 fuel composition extends fuel lifetime by 50% and fuel burnup by 44% at design value of the fuel rod diameter. If the fuel rod diameter for (Th232 + U233)O2 fuel composition is increased to 7.2 mm, fuel lifetime is extended by 105%, and fuel burnup is extended by 38% compared to the design values Текстовый файл |
| Мова: | Англійська |
| Опубліковано: |
2023
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| Предмети: | |
| Онлайн доступ: | https://doi.org/10.1016/j.anucene.2023.109982 |
| Формат: | Електронний ресурс Частина з книги |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=679995 |
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| 200 | 1 | |a Fuel lifetime extension for the KLT-40S small modular reactor by means of thorium-uranium fuel cycle |f S. Beliavskii, M. Balachkov, V. Danilenko, V. Nesterov | |
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| 330 | |a This paper demonstrates the results of the Monte Carlo simulation conducted with MCU-PTR software for a small modular pressurized water reactor KLT-40S. Four dispersed fuel compositions, (U238 + U235)O2, (U238 + Pu239)O2, (Th232 + U235)O2, and (Th232 + U233)O2, were examined for fuel lifetime and fuel burnup calculations. The transition to the (Th232 + U233)O2 fuel composition extends fuel lifetime by 50% and fuel burnup by 44% at design value of the fuel rod diameter. If the fuel rod diameter for (Th232 + U233)O2 fuel composition is increased to 7.2 mm, fuel lifetime is extended by 105%, and fuel burnup is extended by 38% compared to the design values | ||
| 336 | |a Текстовый файл | ||
| 461 | 1 | |t Annals of Nuclear Energy |c Amsterdam |n Elsevier Science Publishing Company Inc. | |
| 463 | 1 | |t Vol. 192 |v Article number 109982, 10 p. |d 2023 | |
| 610 | 1 | |a электронный ресурс | |
| 610 | 1 | |a труды учёных ТПУ | |
| 610 | 1 | |a Small modular reactor | |
| 610 | 1 | |a Pressurized water reactor | |
| 610 | 1 | |a KLT-40S | |
| 610 | 1 | |a Monte-Carlo simulation | |
| 610 | 1 | |a Monte Carlo universal | |
| 610 | 1 | |a Reactivity margin | |
| 610 | 1 | |a Burnup | |
| 610 | 1 | |a Fuel lifetime | |
| 610 | 1 | |a Fissile utilization | |
| 701 | 1 | |a Belyavsky |b S. V. |g Sergey Vladimirovich | |
| 701 | 1 | |a Balachkov |b M. M. |c Specialist in the field of nuclear technologies |c Technician of Tomsk Polytechnic University |f 1995- |g Maxim Mikhailovich |9 22131 | |
| 701 | 1 | |a Danilenko |b V. O. |g Vitaly Olegovich | |
| 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 |9 18749 | |
| 801 | 0 | |a RU |b 63413507 |c 20250429 | |
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| 856 | 4 | |u https://doi.org/10.1016/j.anucene.2023.109982 |z https://doi.org/10.1016/j.anucene.2023.109982 | |
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