Experimental and computational analyses program for radiation source characterization of MOX and high burnup UOX spent fuels
A four year programme (1993-1997) has been launched on spent fuel characterisation for interim dry storage, in order to obtain experimental data for the verification of radiation source evaluation codes for MOX and high burnup UOX spent fuels. Experimental studies include axial distribution along the fuel rod of the neutron emission and fission products, isotope analyses of fuel pellets for actinide and fission products inventory, and EPMA analyses of fuel pellets and material behaviour. Preliminary comparisons of experimental and calculated neutron emission rates indicate that ORIGEN2 and NULIF (detailed neutronic code of NFI) potentially evaluate the radiation source for the high burnup UOX and MOX fuels.
Bibliographic Reference: Paper presented: International Symposium on Spent Fuel Storage : Safety, Engineering and Environmental Aspects, Wien (AT), October 10-14, 1994
Availability: Available from (1) as Paper EN 38833 ORA
Record Number: 199510207 / Last updated on: 1995-02-21
Original language: en
Available languages: en