Моделювання транспорту фотонів в коді Serpent на прикладі розрахунку біологічного захисту
This paper demonstrates the possibilities of the Serpent code as an efficient and reliable tool to calculate the characteristics of gamma radiation field and parameters of the radiation shielding. Normal incidence of photons on an ordinary concrete slab shield from a monoenergetic source is modeled,...
Збережено в:
| Дата: | 2021 |
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| Автори: | , , , , |
| Формат: | Стаття |
| Мова: | Ukrainian |
| Опубліковано: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2021
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| Онлайн доступ: | https://nuclear-journal.com/index.php/journal/article/view/817 |
| Теги: |
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| Назва журналу: | Nuclear and Radiation Safety |
Репозитарії
Nuclear and Radiation Safety| Резюме: | This paper demonstrates the possibilities of the Serpent code as an efficient and reliable tool to calculate the characteristics of gamma radiation field and parameters of the radiation shielding. Normal incidence of photons on an ordinary concrete slab shield from a monoenergetic source is modeled, for a set of photon energies that are typical for the waste fuel radiation. Using the Serpent code, the inverse transmission factors have been evaluated, as well as the build-up factors for photon flux, energy flux, and dose; the dependencies of the evaluated values on shield thickness and source photon energy are analyzed. The obtained dependencies reveal the known typical patterns of photon penetration of ordinary concrete biological shields. The results obtained using the Serpent code comply with the available data obtained by other authors applying other methods, and the results of the XCOM web database. |
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