Feasibility Study on the Utilization of Mixed Oxide Fuel in Korean 900MWe PWR Core Through Conceptual Core Nuclear Design and Analysis

  • Published : 1997.08.01


The neutronic feasibility of typical Korean three-loop 900MWe class PWR core loaded with mixed oxide fuels for both annual and 18-month cycle strategies has been investigated as a means for spent fuel management. For this study, a method of determining equivalent plutonium content was developed under the equivalence concept which gives the same cycle length as uranium fuel. Optimal plutonium zoning within the MOX assembly was also designed with the aim of minimizing the peak md power. Conceptual core designs hate hen developed for equilibrium cycle with the following variations: annual and 18-month cycle, 1/3 and full MOX loading schemes, and typical and high moderation lattice. The analysis of key core physics parameters shows that in all cases considered satisfactory core designs seem to be feasible, though addition of control rod system and change in Technical Specification for soluble boron concentration are required for full MOX loading in order to meet the current design requirements.



  1. Nuclear Europe Worldscan v.3-4 Recycling of Uranium and Plutonium P. Schmiedel
  2. Nuclear Europe v.1-2 Plutonium Recycling in LWRs in F.R. Germany H.J.Dibbert;J.Huber;S.Winnik
  3. Nuclear Technology v.77 Development of Thermal Plutonium Recycling H.J.Roepenack;F.U.Schlemmer;G.J.Schlosser
  4. Nuclear Europe v.5 MOX fuel: an Established Technology in Germany W.Stoll
  5. IAEA Technical Committee Meeting on the Recycling of Plutonium and Urnium in Water Reactor Fuels MOX in France : Status and Prospects C.Golinelli(et. al.)
  6. IAEA Technical Committee Meeting on the Recycling of Plutonium and Urnium in Water Reactor Fuels Plutonium Recycling : EdF's Point of View EdF Nuclear Fuel Branch
  7. IAEA Technical Report Series No.305 Use of MOX fuels: The Reason to Starts H. Bairiot;C. Vandenberg
  8. Nuclear Engineering International Gaining Good Experience with MOX at French PWRs F.Vincent
  9. Nuclear Engineering International EdF gets set for Commercial Plutonium Recycle in LWRs Lewiner
  10. Nuclear Engineering International-Special Publications on French Technology Recycling Pu and Rep. U in Light Water Reactors J.C.Guais;G.Bastard;L.F.Durrent
  11. Nuclear News v.81-82
  12. Nuclear Engineering International Mihama MOX Trials Meet with Success Y.Matsuoka;S.Abeta
  13. International Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems Full MOX Core Design for Advanced PWR H.TOCHIHARA(et. al.)
  14. Nuclear Europe Worldscan A 100% Plutonium-Fueled PWR for 21st Century P. Barbrault
  15. International Conference on the Physics of Reactors, PHYSOR96 An Evaluation of the Development of Moderation-Enhanced MOX Fuel Fully Loaded in Pressurized Water Reactors Y.B. Kim;N.Z.Cho
  16. The Linear Reactivity Model for Nuclear Fuel Management M.J. Driscoll;T.J. Downar;E.E. Pilat
  17. FLOSA: A Multi-cycle Fuel Management Analysis Program, KAERI/TR-469/94 S.Y. OH
  18. Development of TASS-9402 Version, KAERI TR-TS-GEN-94001 H.Y. Yoon