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 discr...
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