This is a repository copy of A coupled level set and volume of fluid method with a reinitialisation step suitable for unstructured meshes.

Processes such as PUREX allow the recovery and reuse of the uranium and the plutonium of GEN II/GEN III reactors and are being adapted for the recycling of the uranium and the plutonium of GEN IV MOX fuels. However, it does not fix the sensitive issue of the long-term management of the high active nuclear waste (HAW). Indeed, only the recovery and the transmutation of the minor actinides can reduce this burden down to a few hundreds of years. In this context, and in the continuity of the FP7 EURATOM SACSESS project, GENIORS focuses on the reprocessing of MOX fuel containing minor actinides, taking into account safety issues under normal and mal-operation. By implementing a three-step approach (reinforcement of the scientific knowledge => process development and testing => system studies, safety and integration), GENIORS will provide more science-based strategies for nuclear fuel management in the EU.

No abstract

This review focuses on consolidating the sequential selective element extraction performed in the process intensification equipment known as Centrifugal Contactors (CCs), the unpredicted precipitation that arises, and finally solutions for inhibiting in situ solids formation.

Uranium carbide is a candidate fuel for future nuclear reactors. However, for it to be implemented in a closed fuel cycle, an outline for its reprocessing is necessary. One proposed method is to oxidise the uranium carbide into uranium oxide which can then be reprocessed using current infrastructure. A mathematical model describing the heat and mass transfer processes involved in such an oxidation has been constructed. The available literature was consulted for reaction coefficients and information on reaction products. A stable and convergent numerical solution has been developed using a combination of finitedifference approximations of the differential equations. Completion times of approximately 3-30 hours are predicted given a spherical pellet with a radius of 9.35 under varying initial conditions. The transient temperature distribution throughout the system is predicted, with a maximum temperature of 1458° observed from an initial temperature of 500° at an oxygen concentration of 3.15 .