Published: Jan 1989
| ||Format||Pages||Price|| |
|PDF Version (216K)||10||$25||  ADD TO CART|
|Complete Source PDF (15M)||10||$156||  ADD TO CART|
A series of passive neutron measurements performed on TIHANGE I spent fuel assemblies were analyzed for comparison with calculated burn-up values and neutron emission rates. The burn-up range of these assemblies was between 10 and 45 MWd/kg and the cooling time varied from 1 to 8 years approximately.
The measurements, performed with 235U fission chambers, were correlated with neutron emission and burn-up by means of the ORIGEN-2 point model depletion code, taking into account the irradiation history. A fairly good correlation was found between the 244Cm contributions, as deduced from the measurements corrected with ORIGEN-2, and the burn-up values as calculated with fuel management codes. It was noticed that the ratio of the calculated (ORIGEN-2) neutron emission and the measured neutron detection varied with the burn-up.
PWR spent fuel, neutron emission rate, burn-up measurement
Paper ID: STP10132S