FA-4108 was operated in the fifth unit of Novovoronezh NPP during fuel cycles 7 9 to an average fuel burn-up of approx. 47 MWd/kgU.
The irradiation histories of 317 fuel rods are presented where variables are given for 30 axial zones in the following forms:
Bu - local burn-up, MWd/kgU;
Ql - local heat rate, kW/m;
T - temperature of cladding inner surface, deg.C;
Ft - neutron fluence (x 10-22), n/s/cm2 (E > 0.1 MEv).
After irradiation, the assembly was shipped to the hot cells of NIIAR Dimitrovgrad where following measurements were made:
- Rod length
- Clad diameter
- Fuel - clad gap
A comparison of the measurements is made with FA-0325 irradiated in the Zaporozskaya VVER-1000 in report 'Geometrical parameters of the fuel rod claddings of the VVER-440 after 4 and 5 fuel cycles and VVER-1000 after 3 and 4 fuel cycles of operation' by Smirnov et al. The report also contains a description of the measuring techniques and an assessment of the measurement errors.
The rod behaviour was modelled using the START-3 code and predictions for individual rods are included in the dataset.
Revision 1 includes the coolant parameters (see "Pre-Characterisation" file).