Heat transfer performance of high temperature and high velocity hydrogen flow and analysis of blockage characteristics

Abstract

In the current situation of increasing demand for nuclear heat propulsion in various countries, the heat transfer characteristics of high temperature and high velocity fluid in the flow channel are particularly important for safe core operation and efficient heat transfer. In order to obtain the flow and heat transfer characteristics of the coolant channel of nuclear thermal propulsion reactor under normal and blocked flow conditions, the numerical method based on commercial CFD software is adopted. Researches by changing the inlet velocity of the coolant channel and the blocking forms of the circular pipe are carried out. The SST k-omega viscous model together with the pressure-based coupling algorithm, which have extraordinary applicability to the model, are adopted. The impulse which are vital to the performance of nuclear heat propulsion is analyzed.

The calculation results indicate that with the increase of the inlet velocity, the coolant outlet impulse increases significantly; The heat transfer deteriorated gradually, and the wall temperature slightly increased; The closer to the center of the pipe the blockage occurred, the higher the pipe temperature became. The research methods and results can provide a reference for the study of the heat transfer characteristics of high temperature and high velocity hydrogen flow, and the heat transfer characteristics and transient simulation initiated by the blockage of the nuclear thermal propulsion reactor.