Development and Preliminary Validation of Three-dimensional Subchannel Thermal-hydraulic Analysis Code CorTAF for Numerical Reactor Core
Reactor core is the pivotal component of nuclear power system, and its integrity is an important prerequisite for safe operation of reactor. Traditional nuclear reactor core thermalhydraulic analysis methods cannot meet the high precision simulation requirements of advanced nuclear power systems i...
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| Format: | Artigo |
| Jezik: | Inglês |
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Editorial Board of Atomic Energy Science and Technology
2022-02-01
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| Serija: | Yuanzineng kexue jishu |
| Teme: | |
| Online dostop: | https://www.aest.org.cn/CN/abstract/abstract21330.shtml |
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