publication . Article . 2015

Mathematical modelling of the pre-oxidation of a uranium carbide fuel pellet

Shepherd, JS; Fairweather, M; Heggs, PJ; Hanson, BC;
Open Access English
  • Published: 05 Dec 2015
  • Publisher: Elsevier
  • Country: United Kingdom
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 finite-difference approximations of the differential equati...
Funded by
Advanced fuelS for Generation IV reActors: Reprocessing and Dissolution
  • Funder: European Commission (EC)
  • Project Code: 295825
  • Funding stream: FP7 | SP5 | Fission

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