Home / Publications / Journals / Nuclear Technology / Volume 25 / Number 1
Nuclear Technology / Volume 25 / Number 1 / January 1975 / Pages 103-112
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24353
Articles are hosted by Taylor and Francis Online.
The heat transfer coefficient between fuel and cladding has been measured in-pile for different types of Zircaloy-2 sheathed fuels: UO2 and UO2-PuO2 pellets, UO2 Vipac, and UO2-PuO2 Sphere-Pac sol-gel. The samples were tested in (a) instrumented rigs, in which fuel and cladding temperatures and nuclear and gamma-ray generated power were directly and continuously measured up to a heat rating of 500 W/cm, and in (b) a hydraulic rabbit at very high rating (over 1000 W/cm). Semiempirical correlations starting from known models of fuel/clad heat transfer, based on strong or weak fuel/clad interaction, fuel cracking, and decrease in gap conductance due to oxide micro layer formation on the cladding internal surface, have been set up to fit the experimental data.