Effect of changing the outer fuel element diameter on thermophysical parameters of KLT-40S reactor unit
| Parent link: | Annals of Nuclear Energy Vol. 190.— 2023.— [109877, 8 p.] |
|---|---|
| Autor corporatiu: | |
| Altres autors: | , , , , |
| Sumari: | Title screen This paper contains the results of KLT-40S reactor unit thermophysical studies and describes its main design features. Such quantities as fuel burnup, Reynolds and Prandtl numbers, coolant flow velocity, temperature distributions for fuel and fuel rod cladding, and departure from nucleate boiling ratio up to boiling crisis were calculated for different fuel rod diameters and fuel compositions. It is shown that changing the dispersed fuel composition from (U238 + U235)O2 to (Th232 + U233)O2 does not alter the maximal temperatures of fuel and fuel rod cladding significantly. An increase in the outer fuel rod diameter up to 7.2 mm leads to a decrease in the maximal temperatures of fuel and fuel rod cladding. Maximal temperatures of fuel and fuel rod cladding do not exceed melting temperatures for silumine and E635 alloy, respectively. Coolant flow velocity for all fuel rod diameters does not exceed 10 m/s and there is no boiling crisis. Режим доступа: по договору с организацией-держателем ресурса |
| Idioma: | anglès |
| Publicat: |
2023
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| Matèries: | |
| Accés en línia: | https://doi.org/10.1016/j.anucene.2023.109877 |
| Format: | Electrònic Capítol de llibre |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=669413 |
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| 200 | 1 | |a Effect of changing the outer fuel element diameter on thermophysical parameters of KLT-40S reactor unit |f S. V. Belyavsky, S. Alkhassan, V. O. Danilenko [et al.] | |
| 203 | |a Text |c electronic | ||
| 300 | |a Title screen | ||
| 320 | |a [References: 26 tit.] | ||
| 330 | |a This paper contains the results of KLT-40S reactor unit thermophysical studies and describes its main design features. Such quantities as fuel burnup, Reynolds and Prandtl numbers, coolant flow velocity, temperature distributions for fuel and fuel rod cladding, and departure from nucleate boiling ratio up to boiling crisis were calculated for different fuel rod diameters and fuel compositions. It is shown that changing the dispersed fuel composition from (U238 + U235)O2 to (Th232 + U233)O2 does not alter the maximal temperatures of fuel and fuel rod cladding significantly. An increase in the outer fuel rod diameter up to 7.2 mm leads to a decrease in the maximal temperatures of fuel and fuel rod cladding. Maximal temperatures of fuel and fuel rod cladding do not exceed melting temperatures for silumine and E635 alloy, respectively. Coolant flow velocity for all fuel rod diameters does not exceed 10 m/s and there is no boiling crisis. | ||
| 333 | |a Режим доступа: по договору с организацией-держателем ресурса | ||
| 461 | |t Annals of Nuclear Energy | ||
| 463 | |t Vol. 190 |v [109877, 8 p.] |d 2023 | ||
| 610 | 1 | |a электронный ресурс | |
| 610 | 1 | |a труды учёных ТПУ | |
| 701 | 1 | |a Belyavsky |b S. V. |g Sergey Vladimirovich | |
| 701 | 1 | |a Alkhassan |b S. |g Samiru | |
| 701 | 1 | |a Danilenko |b V. O. |g Vitaly Olegovich | |
| 701 | 1 | |a Karvan |b R. A. |g Rodion Alekseevich | |
| 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 | |
| 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 |
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| 856 | 4 | |u https://doi.org/10.1016/j.anucene.2023.109877 | |
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