Mechanism Model of Critical Heat Flux in Bundle Based on High-precision Subchannel Code
Critical heat flux (CHF) is a crucial safety limit for PWR core design. Accurately predicting CHF in the core rod bundle channel can enhance the economy and safety of the reactor. Currently, the prediction of rod bundle CHF in engineering is mainly based on specific fuel assembly experiments and sub...
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| Format: | Article |
| Language: | English |
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Editorial Board of Atomic Energy Science and Technology
2023-08-01
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| Series: | Yuanzineng kexue jishu |
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| Online Access: | https://www.aest.org.cn/CN/10.7538/yzk.2023.youxian.0074 |