Abstract
The ACP100 is a small modular reactor with integrated passive design, and the best estimate plus uncertainty method is utilized to conduct a realistic analysis of the loss of coolant accident caused by a double-ended direct vessel injection line break of the ACP100. The thermal-hydraulic system code ARSAC is used, and the figure of merit for reactor safety is determined to be the minimum collapsed core level. Subsequently, important phenomena which may affect the core level are identified, and uncertainty distributions of the inputs are quantified, followed by the uncertainty propagation and sensitivity analysis. The tolerance limit of the minimum collapsed core level is obtained, and the key parameters during different accident phases are identified. According to the results, parameters related to the flow resistance of the injected coolant and some constitutive models of the ARSAC can be optimized to further deepen the reliability and safety design of the ACP100.
Sign-in/Register to access full text options 
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.
