Modern Methods of Radiochemical Reprocessing of Spent Nuclear Fuel


spent fuel, reprocessing, uranium, plutonium, actinides, transmutation

How to Cite

Maltseva, T., ShyshutaА., & Lukashyn, S. (2019). Modern Methods of Radiochemical Reprocessing of Spent Nuclear Fuel. Nuclear and Radiation Safety, (1(81), 52-57.


The paper is devoted to the history of development and the current state of technological and scientific advances in radiochemical reprocessing of spent nuclear fuel from water-cooled power reactors. Regarding spent nuclear fuel (SNF) of NPP power reactors, long-term energy security involves adopting a version of its radiochemical treatment, conditioning and recirculation. Recycling SNF is required for the implementation of a closed fuel cycle and the re-use of regeneration products as energy reactor fuels. The basis of modern technological schemes for the reprocessing of the spent nuclear fuel is the “Purex” process, developed since the 60s in the USA. The classic approach to the use of U and Pu nuclides contained in spent nuclear fuel is to separate them from fission products, re-enrich regenerated uranium and use plutonium for the production of mixed-oxide (MOX) fuel with depleted uranium. The modern reprocessing plants are able to deal with fuel with further increase of its main characteristics without significant changes in the initial project. In order to close the fuel cycle, it is needed to add the following technological steps: (1) removal of high-level and long-lived components and minor actinides; (2) return of actinides to the technological cycle; (3) safe disposal of unused components. Each of these areas is under investigation now. Several new promising multi-cycle hydrometallurgical processes based on the joint extraction of trivalent lanthanides and minor actinides with their subsequent separation have been developed. A number of promising materials is suggested to be potential matrices for the immobilization of high-level components of radioactive wastes. To improve the compatibility of fuel processing with the environment, non-aqueous technologies are being developed, for instance, pyro-chemical methods for the reprocessing of various types of highly active fuels based on metals, oxides, carbides, or nitrides. An important scientific and technological task under investigation is transmutation of actinides. The results of international large-scale experiments on the partitioning and transmutation of fuel with various minor actinides and long-lived fission products confirm the real possibility and expediency of closing the nuclear fuel cycle.


1. Fanghanel Th. (2017). Closing the Nuclear fuel Cycle for Future Sustainable Nuclear Energy. Abstracts of 9th International Conference on Nuclear and Radiochemistry. NRC9. P. 49.

2. International Atomic Energy Agency. Status and Trends in Spent Fuel Reprocessing, IAEA-TECDOC-1467, Vienna, 2005.

3. Wolf, J.-M. (1996). History of the Eurochemic Company. OECD, Paris, 1996.

4. Kiuchi, K., et al. (2002). Technological problems and countermeasures on equipment materials for reprocessing of high-burnup fuels. IAEA-TECDOC-1299. Technical and economic limits to burnup, 2002.

5. International Atomic Energy Agency. Spent Fuel Reprocessing Options, IAEA-TECDOC-1587, Vienna, 2008.

6. Adnet, J., et al. (2005). The development of new hydrometallurgical processes for actinides recovery: The GANEX process. Global 2005, Tsukuba.

7. Ansari S. A., Pathak P., Mohapatra P. K., Manchanda V. K. (2012) Chem. Rev. 112, 1751–1772.

8. Serrano-Purroy D., Baron P., Christiansen B., Glatz J. P., Madic C., Malmbeck R., Modolo G. (2005) Separation and Purification Technology 45, 157–162

9. Modolo G., Wilden A., Geist A., Magnusson D., Malmbeck R. (2012). Radiochim. Acta 100, 715–725.

10. Ossola A., Macerata E., Tinonin D. A., Faroldi F., Giola M., Mariani M., Casnati A. (2015). Radiat. Phys. Chem.

11. Macerata E., Ossola A., Giola M., Faroldi F., Tinonin D. A. Actinide-lanthatide co-extraction by rigidified diglycolamides. Solvent Extraction and Ion Exchange. Vol. 36, Iss 1 (

12. Lavrov G., Ustynyuk N., Gloriozov I., Ustynyuk Yu., Alyapyshev M., Tkachenko L., Babain V. (2017). A novel selective N-heterocyclic ligands for extraction separation of actinides and lanthanides. Abstracts of 9th International Conference on Nuclear and Radiochemistry. NRC9. P.71.

13. Huittinen N., Scheinost A. C., Wilden A., Arinicheva Y. (2017). Cm3+ incorporation in La1-xGdxPO4 monazites: a TRLFS and XAFS study. Abstracts of 9th International Conference on Nuclear and Radiochemistry. NRC9. P.140.

14. Ohta H., Ogataa T., S. Van Winckelb, Papaioannoub D., Rondinella V. V. (2015). Evaluation of Minor Actinide Transmutation Performance in Fast Reactor Metal Fuel Irradiated up to ~6.0 at.% Burnup. Nuclear Science NEA/NSC/R 2.