Abstract
By analysing the neutron noise signals of the in-core detectors, the two-phase flow transit times have been measured for unit 1 of Tarapur Atomic Power Station (General Electric Boiling Water Reactor). Our study has shown that it is reasonable to identify the fluid velocity derived from the measured transit time with the volumetric flux. This interpretation offers the advantage of determining the mass flow rate by using the measured transit time and the steam quality obtained by the heat balance. Further, it is feasible to infer gross flow rate changes by combining the calculated value of the transit time as a function of flow with the periodic measurements of transit time over the operating cycle of the reactor.
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.
