摘要
The accurate prediction of subcooled boiling phenomena in narrow rectangular channels is of great importance for the plate type fuel reactor core safety analysis during some critical scenarios. Serious of experimental studies on subcooled boiling in narrow rectangular channels indicate that a bubble may slide on the heating surface after nucleation and then lift to the main flow, merging with not-yet-fully-grown bubble and disrupting local boundary layer. In this paper, the influence of sliding bubbles is taken into consideration in wall boiling model and implanted into the CFD code to simulate boiling in narrow rectangular channel. Bubble dynamics is used in calculating the relevant bubble diameters during ebulletin cycle. The feasibility of this proposed model is validated with existed experimental data by comparing wall superheat. This work could promote the development of CFD two-phase flow simulation capacity in the plate type fuel nuclear reactor.
| 源语言 | 英语 |
|---|---|
| 页 | 2713 |
| 页数 | 1 |
| 出版状态 | 已出版 - 2019 |
| 活动 | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, 美国 期限: 18 8月 2019 → 23 8月 2019 |
会议
| 会议 | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 |
|---|---|
| 国家/地区 | 美国 |
| 市 | Portland |
| 时期 | 18/08/19 → 23/08/19 |
学术指纹
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