Study on normal operation and failure of pressure control for CN HCCB TBS primary coolant system

Abstract

Based on the design requirement of the test blanket module (TBM) and the design parameters of the helium coolant system (HCS) primary loop, the preliminary design of the pressure control system (PCS), including control logic and main parameters, has been completed. The one-dimensional thermal hydraulic model has been created based on the PCS. According to the operation scenario of international thermal nuclear experimental reactor (ITER), several operating cases, including normal operating cases and PCS failure cases, have been studied. The results show that the PCS design is feasible and the inlet pressure of the TBM can be controlled to remain around 8 MPa. The PCS failures impact the pressure of the HCS as well as the inlet pressure of the TBM severely, while the impacts on the temperature of the TBM are not significant.