Neutronic and burnup analysis of OECD-NEA MOX fuel benchmark with Dragon5 lattice code.

This paper presents a comprehensive and detailed analysis of the OECD-NEA MOX fuel benchmark based on different nuclear data libraries to investigate the reliability and accuracy of the Dragon5 lattice code developed by École Polytechnique de Montréal for the neutronic analysis of mixed uranium-plutonium oxide (MOX) fuel. The neutronics and burn-up calculations for rectangular pin and assembly geometries filled with different compositions of MOX fuel are computed. The performance of different nuclear data libraries is evaluated.

A catalytic mechanism investigation of TiF on hydriding/dehydriding properties of MgCuNi alloy.

In this research, MgCuNi- wt% TiF ( = 0, 2, 4, 6, 8) alloys were synthetized ball milling and the catalytic mechanism of TiF on hydrogenation and dehydrogenation of MgCuNi was studied. The microstructure, hydriding/dehydriding kinetics and thermodynamics of the alloys were discussed in detail. The TiF catalyzed alloys have faster hydriding/dehydriding kinetics and lower thermodynamic stability.