MNSR transient analysis using the RELAP5/Mod3.2 code
To support the safe operation of the Miniature Neutron Source Reactor (MNSR), a thermo-hydraulic transient model using the RELAP5/Mod3.2 code was simulated. The model was verified by comparing the results with the measured and the previously calculated data. The comparisons consisted of comparing th...
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| Автори: | , , |
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| Формат: | Artigo |
| Мова: | Inglês |
| Опубліковано: |
Elsevier
2020-09-01
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| Серія: | Nuclear Engineering and Technology |
| Предмети: | |
| Онлайн доступ: | http://www.sciencedirect.com/science/article/pii/S1738573319308393 |
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