BF3 for Compensation and Additional Emergency Protection in HTGR; Atomic Energy; Vol. 131, iss. 3
| Parent link: | Atomic Energy Vol. 131, iss. 3.— 2022.— [P. 127-130] |
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| Autor principal: | |
| Corporate Authors: | , |
| Outros Autores: | , |
| Resumo: | Title screen The purpose of this work is to investigate materials for effective compensation of excess reactivity in high-temperature gas-cooled reactor plants. The possibility of using gaseous compounds as compensating materials is considered, taking into account an analysis of the distribution spectrum of the neutron flux density and an increase in the microfuel temperature with accumulation of fission products and gaseous compounds. The results of an investigation of the possibility of using boron trifluoride as compensation in the coolant channels of high-temperature gas-cooled reactor installations are presented. Calculations of the change in the reactivity margin with a change in the volume fraction of natural and enriched isotopic boron trifluoride were performed. The calculations were performed using the WIMS-D5B computer program and ENDF/B-VII.0 evaluated nuclear data. Режим доступа: по договору с организацией-держателем ресурса |
| Idioma: | inglês |
| Publicado em: |
2022
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| Assuntos: | |
| Acesso em linha: | https://doi.org/10.1007/s10512-022-00852-w |
| Formato: | Recurso Electrónico Capítulo de Livro |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=668386 |
| Resumo: | Title screen The purpose of this work is to investigate materials for effective compensation of excess reactivity in high-temperature gas-cooled reactor plants. The possibility of using gaseous compounds as compensating materials is considered, taking into account an analysis of the distribution spectrum of the neutron flux density and an increase in the microfuel temperature with accumulation of fission products and gaseous compounds. The results of an investigation of the possibility of using boron trifluoride as compensation in the coolant channels of high-temperature gas-cooled reactor installations are presented. Calculations of the change in the reactivity margin with a change in the volume fraction of natural and enriched isotopic boron trifluoride were performed. The calculations were performed using the WIMS-D5B computer program and ENDF/B-VII.0 evaluated nuclear data. Режим доступа: по договору с организацией-держателем ресурса |
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| DOI: | 10.1007/s10512-022-00852-w |