Transient analysis of the main heat-transfer system of the pool-type sodium-cooled fast reactor

作者：Hongyi Yang, ShaoPu QI, Jun Yang, ShangShang YE, Xiuli Xue · 发表于：Scientia Sinica Technologica · 年份：2021 · DOI：10.1360/sst-2021-0052 · 被引用次数：5 · 研究领域：Nuclear reactor physics and engineering、Nuclear Engineering Thermal-Hydraulics、Heat transfer and supercritical fluids

Sodium-cooled fast reactors are the first choice of the fourth generation of advanced nuclear energy systems. They have attracted significant attention in the development of advanced nuclear energy technology owing to their advantages of proliferative nuclear fuel, transmutation of radioactive waste, and high thermal efficiency power generation. The design and construction of the secondary sodium-cooled fast reactor are ongoing in China. The physical characteristics of fast neutrons and the special thermal, physical, and chemical properties of liquid sodium metal cause special and complex scientific problems in the design of sodium-cooled fast reactors. In this study, taking the energy transfer process of sodium-cooled fast reactors as the object, we establish mathematical and physical models for analyzing large-scale transients in various energy transfer and conversion processes. The model is verified and validated by the natural circulation test of the Phoenix reactor and the international benchmark of the fast flux test facility loss in flow tests. The trend of the calculated values is consistent with that of the test data, and the results are in good agreement. For a typical pool-type sodium-cooled fast reactor, four types of transient events in the power plant are determined by engineering evaluation and deductive analysis. Among them, there are nine normal operation transients, 23 expected transients, 10 abnormal transients, and 7 emergency transients. Based on the esta...