Transient critical heat flux for subcooled boiling of water flowing upward through a vertical small-diameter tube with exponentially increasing heat inputs
Knowledge of transient critical heat flux (CHF) for subcooled boiling of water flow is important for the design of cooling devices such as fusion reactor divertor. Heating occurs rapidly in the divertor and the heat flux is estimated to reach 10 MW/m2 because of plasma disruption. To cope with such...
| Main Authors: | , , , , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
The Japan Society of Mechanical Engineers
2016-12-01
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| Series: | Journal of Thermal Science and Technology |
| Subjects: | |
| Online Access: | https://www.jstage.jst.go.jp/article/jtst/11/3/11_2016jtst0037/_pdf/-char/en |