Abstract
Abstract High temperature gas-cooled reactor (HTGR) has a potential to produce competitive and large amount of carbon-free hydrogen because of its capability to supply high temperature heat of nuclear energy. It is required to establish the control method and system for the HTGR hydrogen production system to maintain its normal operation against the abnormality in the hydrogen production facility. Performances of the control method and system such as readiness and stability have to be demonstrated by transient thermal-hydraulic analysis with a code developed based on RELAP5/MOD3 code. The reactor response against the disturbance in the reactor inlet coolant temperature is revealed in the HTGR hydrogen production system using the control systems. The analytical results showed that the reactor outlet coolant control system enabled to control the variation of the reactor outlet coolant temperature within 4°C against 30°C of large disturbance in the reactor inlet coolant temperature. A variation of the reactor outlet coolant temperature has to be less than 5°C in the simulation to maintain its normal operation in the HTGR hydrogen production system. Thus, the effectiveness of the control method was confirmed. The simulations code and results will be validated through a HTTR thermal load fluctuation test.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
