Research Progress on Relaxed Two-pressure Two-fluid Model and Algorithm
An accurate two-phase flow model is an important basis for nuclear reactor safety analysis. The classical two-fluid six-equation model used in many current thermal-hydraulic programs has an ill-posed problem, if a small disturbance is introduced, the system parameters will oscillate greatly, resulti...
| Published in: | Yuanzineng kexue jishu |
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| Main Author: | |
| Format: | Article |
| Language: | English |
| Published: |
Editorial Board of Atomic Energy Science and Technology
2023-03-01
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| Subjects: | |
| Online Access: | https://www.aest.org.cn/CN/10.7538/yzk.2022.youxian.0562 |