Abstract
A mechanistic critical heat flux correlation has been developed for a wide range of operating conditions which include low mass fluxes of 540–890 kg/m2-s, high pressures of 12–13 MPa, and critical heat fluxes of 835–1100 kW/m2. Eleven experimental data points have been collected over these conditions to inform the development of the model using bundle geometry. Errors of within 15% have been obtained with the proposed model for predicting the critical heat flux value, location, and critical pin power for a non-uniform heat flux applied to a 2 × 2 bundle configuration.
Original language | English |
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Pages (from-to) | 604-611 |
Number of pages | 8 |
Journal | Nuclear Engineering and Design |
Volume | 310 |
DOIs | |
State | Published - Dec 15 2016 |
Externally published | Yes |
Funding
This material is based upon work supported by the Department of Energy Nuclear Energy University Programs grant in collaboration with the University of Wisconsin-Madison .
Funders | Funder number |
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DOE Office of Nuclear Energy | |
University of Wisconsin-Madison |
Keywords
- Boiling crisis
- CHF
- Critical heat flux
- Japan-US seminar
- Two-phase