The China EU cooperation project SCWR-FQT small experimental reactor is selected as the research object. The new SCWR-FQT calculation code is made. Thermal performance of four channels are analyzed. The results show that: During normal condition, the coolant temperature increases gradually and pressure reduces gradually. The highest temperature of the coolant does not exceed 450°C working limit, meets the design safety requirement. When transient of entrance temperature occurs, lateral two channels are affected significantly. The inside channel has maximum temperature stability because of the minimum affection. The increasing of the entrance temperature will shorten the time of the relative inner two channels to reach stable. When transient of entrance flow occurs, the inside channel has the maximum affection. The decreasing of the entrance flow will increase the time of the inside channel to reach stable. The entrance flow should not lower than 49.2% of the normal operating mode.
- Nuclear Engineering Division
Thermal-Hydraulic Analysis for Experimental Device of Supercritical Water Reactor-Fuel Qualification Test
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Liu, L, Zhou, T, Li, Y, Cheng, W, Chen, J, Huang, S, & Huang, Y. "Thermal-Hydraulic Analysis for Experimental Device of Supercritical Water Reactor-Fuel Qualification Test." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition. Prague, Czech Republic. July 7–11, 2014. V005T17A025. ASME. https://doi.org/10.1115/ICONE22-30176
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