Порівняння малогрупових бібліотек нейтронно-фізичних констант CASMO i NESSEL та їх використання в програмі DYN3D
This work presents comparative analysis of two group diffusion cross sections libraries which were generated by NESSEL-4 and CASMO-4 lattice codes. Diffusion parameters were calculated for WER-1000 fuel assemblies with stainless steel spacing grids and guiding tubes. These cross section sets were in...
Збережено в:
| Дата: | 2007 |
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| Автори: | , , |
| Формат: | Стаття |
| Мова: | English |
| Опубліковано: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2007
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| Онлайн доступ: | https://nuclear-journal.com/index.php/journal/article/view/1070 |
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| Назва журналу: | Nuclear and Radiation Safety |
Репозитарії
Nuclear and Radiation Safety| Резюме: | This work presents comparative analysis of two group diffusion cross sections libraries which were generated by NESSEL-4 and CASMO-4 lattice codes. Diffusion parameters were calculated for WER-1000 fuel assemblies with stainless steel spacing grids and guiding tubes. These cross section sets were introduced into reactor core code DYN3D and tested on the base of real reactor core states. In this case operation data of the first three fuel cycles of 6-th unit of Zaporizhzhya NPP were used.
The work was performed in the framework of the order В MU SR 2511 - 862 500/09, UA-2575. The report describes the opinion and view of the contractor - TUV ENERGIE CONSULT - and does not necessarily represent the opinion of the ordering party - Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) mbH. |
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