Special features of assessing the strength of nuclear reactor equipment under dynamic loads
| Autor: | K. A. Lonin, V. A. Panov, V. L. Patrushev, D. V. Savchuk, S. A. Soloviev |
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| Jazyk: | English<br />Russian |
| Rok vydání: | 2023 |
| Předmět: | |
| Zdroj: | Вестник Самарского университета: Аэрокосмическая техника, технологии и машиностроение, Vol 22, Iss 2, Pp 57-66 (2023) |
| Druh dokumentu: | article |
| ISSN: | 2542-0453 2541-7533 |
| DOI: | 10.18287/2541-7533-2023-22-2-57-66 |
| Popis: | The paper presents tasks and approaches to their solutions in assessing vibration strength and dynamic safety of marine reactor equipment (for example: pumps, control driven rod mechanisms). The topicality of this work is determined by the experience of operating nuclear power plants. Development of digital computation models and computational analysis allowed us to exclude experimental validation of control driven rod mechanisms seismic resistance. A digital computational model was developed for validating the dynamic safety and life time of the seal pot of the reactor facility main circulation pump. The model included the main circulation pump and the framework of the reactor facility. Computational and experimental analysis of the vibration state of the control and protection system drives was also carried out. |
| Databáze: | Directory of Open Access Journals |
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