NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070018(2025)
Experimental study on flow instability in parallel helical tubes
Fig. 2. Thermocouples distribution at the same temperature measuring cross-section
Fig. 3. Influence of system pressure on flow instability in parallel helical tube (color online)(a) G=300 kg∙m-2∙s-1, (b) G=500 kg∙m-2∙s-1
Fig. 4. The influence of system pressure on critical heat load of parallel helical tube (color online)(a) G=300 kg∙m-2∙s-1, (b) G=500 kg∙m-2∙s-1
Fig. 5. The influence of inlet mass flow rate on critical heat load of parallel helical tube (color online) (a) P=7 MPa, (b) P=11 MPa, 13 MPa
Fig. 6. The influences of coiled diameter on the stable boundary of the system (color online) (a) P=11 MPa, G=300 kg∙m-2∙s-1, (b) P=11 MPa, G=500 kg∙m-2∙s-1, (c) P=7 MPa, G=300 kg∙m-2∙s-1, (d) P=7 MPa, G=500 kg∙m-2∙s-1
Fig. 7. The influences of subcooling degree on gas-liquid length ratio and stable boundary (color online) (a) P=7 MPa, G=500 kg∙m-2∙s-1, (b) P=11 MPa, G=500 kg∙m-2∙s-1, (c) P=11 MPa, G=300 kg∙m-2∙s-1
Fig. 8. The oscillation periods under different system pressure conditions (color online)
Fig. 9. The variation of T/τ with air voids xin under different system pressure conditions (color online)
Fig. 10. The variation of oscillation periods of HT-1 and HT-3 with air voids at different inlet quality (color online) (a) P=7 MPa, (b) P=11 MPa
Fig. 11. The variation of T/τ of HT-1 and HT-3 with air voids at different inlet quality (color online)(a) P=7 MPa, (b) P=11 MPa
Fig. 13. Comparation of measured values in system boundary experiment with predicted value of straight pipe model (color online)(a) P=11 MPa, G=300 kg∙m-2∙s-1, (b) P=11 MPa, G=500 kg∙m-2∙s-1, (c) P=7 MPa, G=300 kg∙m-2∙s-1, (d) P=7 MPa, G=500 kg∙m-2∙s-1
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Xiong ZHENG, Tianming RUAN, Yisong HU, Yaxin GAO, Shuqi MENG, Dechang CAI, Yulong MAO. Experimental study on flow instability in parallel helical tubes[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070018
Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering
Received: Mar. 2, 2025
Accepted: --
Published Online: Sep. 15, 2025
The Author Email: Xiong ZHENG (x.zheng.ty@foxmail.com)