Knowledge of fuel limits and safety margins in normal and off-normal transients in nuclear power plants remains a constant preoccupation for electricity producers and fuel manufacturers. Accurate determination of such limits, through fuel irradiation testing in the OSIRIS reactor at Saclay is closely linked to the reliability of appropriate instrumentation techniques. Two paths are currently fo...

Zirconium (Zr) alloy is a promising fuel cladding material used widely in nuclear reactors. Usually, it service for long time under the effects of neutron radiation with high temperature and pressure, which results thermomechanical coupling behavior during process. Focusing on UO2/Zr elements, macroscopic responses pure Zr, Zr-Sn, Zr-Nb binary system alloys, as well Zr-Sn-Nb ternary materials, ...

Nuclear-grade zirconium alloys properties are very similar to those of pure (Zr), because in most cases they contain more than 95% Zr atoms. They have extensive application nuclear industry, especially fuel cladding. Lattice and Zr-1%Nb alloy been explored this study. Point defect formation energies also calculated. Then, di-vacancies considered check the cluster vacancy production. In next sec...

The influence of the nuclear fuel cladding pre-oxidation on post-LOCA quench resistance was experimentally studied and then modeled. Adopting a separate effect approach, quenched high temperature oxidized samples were axially loaded in mechanical device. pre-existing oxide layer shows complex that interpreted modeled using simple approach reproducing main observed phenomena. A new correlation e...

This analysis of Kuosheng nuclear power plant (NPP) was performed mainly by TRACE, assisted with FRAPTRAN and FRAPCON. SNAP v2.2.1 and TRACE v5.0p3 are used to develop the Kuosheng NPP SPU TRACE model which can simulate the turbine trip without bypass transient. From the analysis of TRACE, the important parameters such as dome pressure, coolant temperature and pressure can be determined. Throug...

In this paper, we propose an alternative process based on spark plasma sintering for the manufacture of nuclear fuel plates research reactors. This presents significant flexibility to control manufacturing parameters such as meat geometry and porosity according designer specifications. Furthermore, it allows increase uranium loading up 7.3 gU cm−3, exceeding current requirements high performanc...