Abstract
The characteristics of the passive residual heat removal system (PRHRS) are very important for the safety of the modular high temperature gas-cooled reactor (MHTGR). In this study, a one-dimensional code used to calculate the transient characteristics of the PRHRS of the 10 MW High Temperature Gas-cooled Test Reactor (HTR-10) was developed using the C programming language. Water loop and air cooled condenser are the crucial parts of the PRHRS. Their characteristics under the startup condition, normal operating condition and shutdown condition of HTR-10 were respectively calculated with the one-dimensional code. To validate the code, the computational results were compared with the experimental results obtained from the HTR-10. Also, the flow and heat transfer conditions in the water loop and the air cooled tower were also analyzed. The results show that the computational results are in good agreement with the experimental results. Under the normal operating condition, the characteristics of the PRHRS are mainly affected by the environmental temperature. Under the startup condition and the shutdown condition, the characteristics of the PRHRS are affected by both the nuclear power and the environmental temperature, and the effects of the nuclear power play a dominant role.
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