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Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor
Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average equilibrium refueling. The results show that the coolant...
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| Main Authors: | , , , , , , , |
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| Formato: | Artigo |
| Idioma: | Inglês |
| Publicado em: |
Elsevier
2019-04-01
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| Colecção: | Nuclear Engineering and Technology |
| Acesso em linha: | http://www.sciencedirect.com/science/article/pii/S1738573318305321 |
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