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To develop target materials for high burn-up and suitable for the separation process. REFERENCES 1 Haug, H. , "Anfall, Beseitigung und relative Toxizitat langlebiger Spaltprodukte und Aktiniden in der radioaktiven Abfallen der Kernbrennstoffzyklen", KFK-2022, Kernforschungszentrum Karlsruhe, November 1975. 2 Olson, G. , "BEGAFIP. Programvard, utveckling och bench-mark berakningar", SKBF TR 80-20, Svensk Karnbransleforsorjning AB, Stockholm, December 1980 (in Swedish). 3 Liljenzin, J. , "Some Estimates of the Total Nuclide Inventory in the Year 2100 from Swedish Nuclear Power Production", SKI Technical Report 90:18, Swedish Nuclear Power Inspectorate, Stockholm, April 1990.

This principle has not been applied and fulfilled in those so far developed and designed systems for spent solid fuel management. There is an adequate technology which only utilizes nuclear processes and which can transfer the high level and long-lived radionuclides towards short-lived or even stable nuclides-transmutation technology performed in a suitable nuclear reactor device and combined with a continuous separation of certain components of its core or reprocessing of the reactor fuel so as to avoid the consequent induction of radioactivity by neutron irradiation of stable and short-lived nuclides.

The Figure also indicates where reprocessing and separation processes have to be used. In this context it is important to understand the possibilities and limitations of these processes. The following facts are important: i) The fuel/target material after irradiation is the input to the separation process. ii) The process separates chemical elements regardless of their isotopic composition (isotope separation is possible, but costly, and must be added after the chemical separation). iii) The primary output of the process is either new fuel/target material in the proper chemical/physical form or raw material to a separate fuel/target fabrication process.

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Advanced Fuels with Reduced Actinide Generation (IAEA TECDOC-0916)


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