Abstract
Boiling heat transfer condition has significance for pool-type research reactors cooled by natural circulation. It has important effect on the fuel element safety of reactor. On the basis of heat transfer characteristics of the Xi’an pulsed reactor (XAPR), fuel conduction, single-phase convection and boiling heat transfer, and void fraction models of the core are constructed. To validate the correctness of the physical models presented in the paper, numerical calculation based on a subchannel analysis method of XAPR is carried out, and the temperature fields are measured in some reactor coolant channels. The comparison between the calculated and experimental results verifies the effectiveness of the models. These physical models are used to calculate the thermal-hydraulic parameters of XAPR at the rated power (for XAPR the rated power is 2.0 MW in steady-state operation). The results indicate that subcooled boiling occurs in the XAPR core but it exhibits a subcooling degree which is considerably higher than that of saturation boiling. Subcooled boiling improves the efficiency of heat transfer between the fuel element surface and coolant, as well as effectively protects fuel elements. This research is also a beneficial reference in thermal-hydraulic analysis for other natural circulation reactors.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
