Abstract
Neutron emission rates for irradiated BWR fuel bundles were measured and compared with calculated results. The axial thermal neutron flux distributions outside the channel box of the fuel bundles were measured by means of Au-foil activation technique and converted into neutron emission rate using the calculated conversion factors. The decay of neutron emission rate was also measured and the contribution of 242Cm to neutron emission was evaluated from the results. Calculations were carried out using the lattice cell burnup calculation code and two-dimensional diffusion code. Spontaneous fission and 18O(α, n)21Ne reaction were considered as the neutron-producing processes, and eight transuranium nuclides essential to neutron emission were taken into account. For the magnitude of neutron emission rate, calculations showed reasonable agreements with measurements in view of the accuracy of nuclear data used. However, some systematic discrepancies between calculations and measurements were found and these discrepancies are considered to have resulted from the biases in the calculated exposure values.
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.
