Investigative study of the radiation damage on fuel clad of miniature neutron source reactor using computational tools; Journal of Physics: Conference Series; Vol. 2064 : Gas Discharge Plasmas and Their Applications (GDP 2021)
| Parent link: | Journal of Physics: Conference Series Vol. 2064 : Gas Discharge Plasmas and Their Applications (GDP 2021).— 2021.— [ 012103, 6 p.] |
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| Sažetak: | Title screen Core conversion requires some evaluation of the reactor safety. Changes to the reactivity worth, shutdown margin, power density and material properties are crucial to the proper functioning of the reactor. The focus of this article is to study the neutron flux distribution in the reactor core and radiation damage on candidate clads. The Ghana Research Reactor-1 (GHARR-1) operates at maximum power of 30 kW in order to attain a flux of 1.0? 1012 n·cm–2·s for the high enriched uranium core. Using the GHARR-1 core geometry, considering 348 fuel pins, the multiplication factor (Keff) is calculated at enrichments of 10%, 12.5%, 16%, 20%, 30% and 90.2%. The spectrum of neutron flux generated in the 26 group is also calculated at the specified enrichments. The ion/particle interactions with the targets (clad) were studied in the Stopping and Range of Ion in Matter code to establish the best clad material based on recorded defects and vacancies generated. From the calculations and simulations, the best choice from the candidate clads based on the assessment is SiC. The calculation of the fuel campaign length gives 7.5 years. The defects sustained by the prospective clad showed low susceptibility to swelling and other forms of deformation. |
| Jezik: | engleski |
| Izdano: |
2021
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| Teme: | |
| Online pristup: | http://earchive.tpu.ru/handle/11683/72799 https://doi.org/10.1088/1742-6596/2064/1/012103 |
| Format: | Elektronički Poglavlje knjige |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=667943 |
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| 200 | 1 | |a Investigative study of the radiation damage on fuel clad of miniature neutron source reactor using computational tools |f S. Alkhassan, S. V. Belyavsky, V. N. Nesterov | |
| 203 | |a Текст |c электронный | ||
| 300 | |a Title screen | ||
| 320 | |a [References: 9 tit.] | ||
| 330 | |a Core conversion requires some evaluation of the reactor safety. Changes to the reactivity worth, shutdown margin, power density and material properties are crucial to the proper functioning of the reactor. The focus of this article is to study the neutron flux distribution in the reactor core and radiation damage on candidate clads. The Ghana Research Reactor-1 (GHARR-1) operates at maximum power of 30 kW in order to attain a flux of 1.0? 1012 n·cm–2·s for the high enriched uranium core. Using the GHARR-1 core geometry, considering 348 fuel pins, the multiplication factor (Keff) is calculated at enrichments of 10%, 12.5%, 16%, 20%, 30% and 90.2%. The spectrum of neutron flux generated in the 26 group is also calculated at the specified enrichments. The ion/particle interactions with the targets (clad) were studied in the Stopping and Range of Ion in Matter code to establish the best clad material based on recorded defects and vacancies generated. From the calculations and simulations, the best choice from the candidate clads based on the assessment is SiC. The calculation of the fuel campaign length gives 7.5 years. The defects sustained by the prospective clad showed low susceptibility to swelling and other forms of deformation. | ||
| 461 | 0 | |0 (RuTPU)RU\TPU\network\3526 |t Journal of Physics: Conference Series | |
| 463 | |t Vol. 2064 : Gas Discharge Plasmas and Their Applications (GDP 2021) |o 15th International Conference, 5-10 September 2021, Ekaterinburg, Russia |v [ 012103, 6 p.] |d 2021 | ||
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| 700 | 1 | |a Alkhassan |b S. |g Samiru | |
| 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 | |
| 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/10.1088/1742-6596/2064/1/012103 |z https://doi.org/10.1088/1742-6596/2064/1/012103 | |
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