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Extra info for Long-Term Storage of Spent Nuclear Fuel (IAEA TECDOC-1293)
It is also seen as important to obtain reliable data, to demonstrate safety performance and to support design work for long term storage. ) see Figures 21 and 22. This work is conducted in collaboration with the French utility company EDF. During interim storage, the intrinsic evolution of SF (matrix and cladding) is expected to take place within a closed system with no exchange of matter with the external medium. Helium will be produced by Pu daughters and for MOX fuel significant amounts can be expected, see 44 Figure 23.
45 FIG. 18. SF multipurpose package — storage design trends. FIG. 19. SF multipurpose package for storage canister — design trends. 46 FIG. 20. Conclusions. FIG. 21. R&D programme objectives. 47 FIG. Radionuclide source terms, French model. FIG. 23. 5 MW·d/t U UOX and MOX. 3. GERMANY The main objective of the R&D-work is to assess and assure the integrity of the fuel under changing boundary conditions such as increasing burnup, improved materials or longer periods of time. Since licensing aspects are closely linked to this topic, the following chapters cover both.
Other NPPs are to adopt similar AFR dry storage facilities. The United States of America stores approximately 95% of its spent fuel at reactor pools. Storage in many pools has been increased over the years with high density racks. Some utilities are using additional dry storage systems at their reactor sites. Currently more than 2,000 t HM of spent fuel are stored under dry conditions at 17 sites in 13 states. Several different systems are in use: NUHOMS, VSC, CASTOR-casks, TN-casks, NAC-casks, MC, and TranStor.