Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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A CONCEPTUAL STUDY OF PYROPROCESSING FOR RECOVERING ACTINIDES FROM SPENT OXIDE FUELS

  • Published : 2008.12.31
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Abstract

In this study, a conceptual pyroprocess flowsheet has been devised by combining several dry-type unit processes; its applicability as an alternative fuel cycle technology was analyzed. A key point in the evaluation of its applicability to the fuel cycle was the recovery yield of fissile materials from spent fuels as well as the proliferation resistance of the process. The recovery yields of uranium and transuranic elements (TRU) were obtained from a material balance for every unit process composing the whole pyroprocess. The material balances for several elemental groups of interest such as uranium, TRU, rare earth, gaseous fission products, and heat generating elements were calculated on the basis of the knowledge base that is available from domestic and foreign experimental results or technical information presented in open literature. The calculated result of the material balance revealed that uranium and TRU could be recovered at 98.0% and 97.0%, respectively, from a typical PWR spent fuel. Furthermore, the anticipated TRU product was found to emit a non-negligible level of $\gamma$-ray and a significantly higher level of neutrons compared to that of a typical plutonium product obtained from the PUREX process. The results indicate that the product from this conceptual pyroprocessing should be handled in a shielded cell and that this will contribute favorably to retaining proliferation resistance.

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References

  1. Hee-Seong Shin, Nuclear data obtained from the ORIGEN2, v2.1, 'Spontaneous fission neutron source from irradiation of PWR fuel', Korea Atomic Energy Research Institute, 2007
  2. Jang-Jin Park et al, 'Development of voloxidation technology for PWR spent fuels', KAERI/RR-2840 (2006)
  3. Sang-Mun Jeong et al, 'Inactive test of the electrolytic reduction system in the ACP hot cell', KAERI/TR-3170 (2006)
  4. M.Salvatores et al, 'Assessment of pyrochemical processes for separation/transmutation strategies', PG-DRRV/Dir/00-92, CEA, France (2000)
  5. Jae-Hyung Yoo et al, 'Pyrometallurgical Process of Actinide Metals', KAERI/AR-540 (1999)
  6. Jae-Hyung Yoo, Han-Soo Lee and Eung-Ho Kim, 'Prediction of a mutual separation of actinide and rare earth groups in a multistage reductive extraction system', Nucl. Eng. & Tech. 39, 5 (2007) https://doi.org/10.5516/NET.2007.39.5.663
  7. Jae-Hyung Yoo et al, 'Development of transmutation technology for long-lived radionuclides', KAERI/RR-2810 (2006)
  8. Jang-Jin Park et al, 'Trapping Technology for Gaseous Fission Products from Voloxidation Process', KAERI/TR-3047 (2005)
  9. Jae-Hyung Yoo et al, 'Design study of advanced nuclear fuel cycle system(II)-Establishment of the concept of the recycle system using molten salt', KAERI/TS-196, 2004 (Translation report of JNC TN 9400 98-003)
  10. G.R.Choppin et al, committee on electrometallurgical techniques for DOE spent fuel treatment, USA, 'Electrometallurgical Techniques for DOE Spent Fuel Treatment', National Academy Press, Washington, D.C. (2000)
  11. Laurie M. Unger, D.K.Trubey, 'Specific Gamma-ray Dose Constants for Nuclides Important to Dosimetry and Radiological Assessment', ORNL/RSIC-45/RI, Oak Ridge National Laboratory (1982)
  12. W.H.Hannum, D.Wade and G. Stanford, 'Self-Protection in Dry Recycle Technologies', Argonne National Laboratory, Proc. Global ''95, p.83 (1995)
  13. L.Koch, T.Inoue, T.Yokoo, 'A Safer Nuclear Fuel Management Strategy without Sensitive Technology and Weapon Useable Material', Proc. Global 2005, Tsukuba, Japan, Oct 9-13, 2005
  14. Keun-Il Park et al, 'Hot Experiment on Fission Gas Release Behavior from Voloxidation Process using Spent fuel', KAERI/TR-3448 (2007)
  15. J.A.Stone, D.R.Johnson, 'Measurement of Radioactive Gaseous Effluents from Voloxidation and Dissolution of Spent Nuclear Fuel', DP-MS-78-7, Savannah River Lab. (1978)
  16. G.S.You et al, 'Conceptual Design Report of Hot Cell Facilities for demonstration of Advanced Spent Fuel Management Process', p.7, KAERI/TR-2092 (2002)
  17. K.Kinoshita et al, 'Separation of Uranium and Transuranic Elements from rare earth Elements by Means of Multistage Extraction in LiCl-KCl/Bi System', J. Nucl. Sci. and Tech. 36, 2 p.189-197 (1999) https://doi.org/10.3327/jnst.36.189
  18. S.Herrmann, S.Li and M. Simpson, 'Electrolytic Reduction of Spent Light Water Reactor Fuel', J. Nucl. Sci. and Tech. 44, 3 p.361-367 (2007) https://doi.org/10.3327/jnst.44.361

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