<p>As a critical component for pool-type Sodium cooled Fast Reactor (SFR), the main vessel plays a major role in holding the entire sodium in the pool. The Reactor Vessel Cooling System (RVCS) contributes to the cooling of the main vessel. This paper develops a one-dimensional code and the numerical analysis has been conducted to evaluate the thermal-hydraulic characteristics of RVCS for China Experimental sodium-cooled Fast Reactor (CEFR). Firstly, the code is applied to the analysis on the steady characteristics of RVCS and the results are compared with the design value. The simulation results show that the main vessel is cooled effectively and the comparison results are in good agreement with the design value. Then, the code is coupled with the Transient Thermal-Hydraulic Analysis Code for Sodium-cooled fast reactors (THACS) in order to study the transient characteristics of RVCS. The simulation finds that a reverse flow in RVCS is showed up and RVCS could take the decay heat effectively, which also contributes a lot to the core cooling. Based on the simulation, it can be concluded that RVCS has great effect on the main vessel cooling and the code could evaluate the thermal-hydraulic characteristics as well as the decay heat removal capacity of RVCS.</p>

Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor

Paper Proceedings: https://asmedigitalcollection.asme.org/ICONE/ICONE28/volume/85246

2021 28th International Conference on Nuclear Engineering (ICONE28)

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