摘要
PWR core phenomena can be simulated and predicted more precisely and in more details with high-fidelity neutronics and thermal-hydraulics coupling calculation. An in-house subchannel code SUBSC was developed as the thermal-hydraulics solver. The steady-state bundle benchmark of PSBT benchmark was calculated to validate SUBSC; the results showed that the channel-averaged quality provided by SUBSC agreed well with the measured data at various conditions. Then a coupling code written in python language was employed to couple SUBSC and the Monte Carlo code OpenMC. The coupling code SUBSC/OpenMC was applied for a typical PWR 3x3 pin cluster coupling calculation. The numerical results demonstrated that the subchannel code SUBSC developed in this paper is applicable for high-fidelity coupling calculation.
| 源语言 | 英语 |
|---|---|
| 页(从-至) | 264-274 |
| 页数 | 11 |
| 期刊 | Energy Procedia |
| 卷 | 127 |
| DOI | |
| 出版状态 | 已出版 - 2017 |
| 活动 | International Youth Nuclear Congress, IYNC 2016 - Hangzhou, 中国 期限: 24 7月 2016 → 30 7月 2016 |
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