Development of a test task for coupled neutronic and thermal-hydraulic analysis of LFR fuel cell
In the absence of operational experience with Generation IV reactors and limited experimental data, developing test tasks is crucial for ensuring the safety and reliability of novel reactor designs. This study presents a test task for coupled neutronic and thermal-hydraulic analysis of a lead-cooled...
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| Автори: | , , , , , |
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| Формат: | Artigo |
| Мова: | Inglês |
| Опубліковано: |
Elsevier
2025-11-01
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| Серія: | Nuclear Engineering and Technology |
| Предмети: | |
| Онлайн доступ: | http://www.sciencedirect.com/science/article/pii/S1738573325003316 |
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