Abstract
The delayed neutron measurement has been used for the fresh fuel inspection and 235U enrichment measurement of uranium materials for many years. The origin of delayed neutron is the beta decay of fission fragments and the population of fission fragments of right after a fission event decreases as time goes by. In the process of optimization of delayed neutron measurement system using a DT neutron generator to determine the fissile content of spent fuel assembly, we could find out that the utilization of delayed neutron can be maximized by performing the data acquisition of delayed neutron in an earlier time after the fission event. Monte Carlo code simulation results show the delayed neutron count rate obtained in a high frequency mode (100 Hz) is 3.25 times bigger than that acquired in a low frequency mode (0.5 Hz). The influence of delayed neutrons by 238U fission on delayed neutron counts is not negligible. Thus the delayed neutron count rate for 64 cases of spent fuel assembly is corrected by considering the 238U influence. To obtain sufficiently large ratios of signal to background for many cases of spent fuel assembly, 1010 ∼ 1011 n/s strength of DT neutron generator is needed.
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.
