Published April 2004 | Version v1
Report

Qualification of power determination and in-pile measurements in the UO2 Gd2 02 fuel irradiation test IFA 636

Description

IFA-S36 is irradiated with the main objective of extending the database on the performance of UO2Gd2O2 fuel (with 8% absorbing gadolinia isotopes) compared with commercial UO2. The rig carries 6 rods in the lower cluster (including three Gd-doped fuel rods) and 3 rods in the upper cluster (one rod with Gd-doped fuel). The rods are instrumented with expansion thermometers (ETs), fuel and cladding elongation detectors (EFs and ECs) and pressure transducers (PFs). Repeated calorimetric power measurements, physics calculations by the HELIOS code and gamma scans of selected rods in both clusters enabled the power and burnup determination to be qualified and corrected. The data suggest that as of May 2004 the power ratings in both fuels are much alike and burnups are about 30 and 34 MW/kgUO2 in the Gd-doped and ordinary UO2 rods respectively. Analysis of in-pile measurements compared with calculations shows that neutron absorption affects fuel temperature, power and burnup radial distributions in Gd-doped fuel at BOL compared with UO2 fuel. Sensitivity analyses performed with the HELIOS and FTEMP3 codes show that fuel centreline temperature in Gd-doped fuel is influenced by radial power depression, depletion of fissile materials and absorbing Gd isotopes as well as thermal conductivity of the fuel matrix and its degradation during irradiation. Analysis of the fuel dimension changes revealed densification only in the UO2 fuel whereas fuel elongation measurements in the Gd-doped fuel rods indicated essentially constant swelling with burnup. At burnups above 5 MWd/kgUO2 the swelling rate was about 0.5-O.fi % ΔV/V per 10 MWd/kgUO2 for both fuel types. Internal pressure measured in the Gd-doped rod at BOL showed slight fuel densification and possibly He gas absorption, whereas derived swelling rate was somewhat Iarger than values obtained from the fuel elongation measurements. Cladding elongation measurements showed no substantial PCMI in the Gd-doped fuel rods whereas for the UO2 rod some PCMI effects were seen to occur during reactor operation at different burnups. (Author)

Availability note (English)

Available from IFE, PO Box 173, 1751 Halden Norway

Additional details

Publishing Information

Imprint Pagination
24 p.
Report number
HWR--767

Optional Information

Notes
refs., figs., tabs