Author:
Zhou Jinxuan,Yang Lei,Guo Bin,Zhu Lili,Li Weibao,Liu Zhe,Yao Lidong,Xu Qianglin
Abstract
Abstract
The Chinese Fusion Engineering Testing Reactor (CFETR) aims at providing technical support and data reference for future fusion demonstration reactor. The vacuum vessel primary heat transfer system (VV PHTS), playing a vital role in guaranteeing the safety operation of tokamak device, which is a part of the tokamak cooling water system. It will operate in three main modes: plasma operation, water baking and decay heat removing. The design of the VV PHTS should have three functions corresponding to the above modes. Based on the thermal-hydraulic requirements, the system process have been proposed. The concept design of the system has been performed including pipes and pressurizer. For the purpose of obtaining the parameters of other main components and predicting the system operating behaviour, the thermal-hydraulic analysis model has been developed by using AFT fathom mode. The steady-state results of all three operating modes such as velocity and pressure show that the designed VV PHTS and selected methodology are feasible.
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