An International Spent Nuclear Fuel Storage Facility Exploring a Russian Site as a Prototype: Proceedings of an International Workshop (2005) / Chapter Skim
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Utilization of High-Level Waste -- Types of High-Level Radioactive Wastes Formed as a Result of Dry Methods of Spent Fuel Regeneration and Technologies for their Management
Utilization of High-Level Waste -- Types of High-Level Radioactive Wastes Formed as a Result of Dry Methods of Spent Fuel Regeneration and Technologies for their Management
Pages 187-198
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From page 189... ...
A safety analysis has shown the fundamental advantages of the pyroelectrochemical regeneration technology in comparison with currently used water-based methods for reprocessing spent nuclear fuel. The basic safety aspects and physical-chemical properties of the process on which it is based are presented in Box 1.
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From page 190... ...
. It is obvious that after regeneration, the fuel contains not only fission products but also minor actinides.
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From page 191... ...
-106 1.3 · 101 Sb-125 2.1 · 103 Cs-134 1.9 · 105 Cs-137 2.0 · 104 Ce(Pr) -144 5.3 · 102 Eu-152 1.4 · 103 Eu-154 5.8 · 104 Eu-155 2.0 · 103 Corrosion elements: Mn-54 at 5.9 · 105 and Co-60 at 3.2 · 106 Curies per gram of PuO2 Cation additives 8.86 mass percent of the mass of PuO2 and by nomenclature Si, Fe, Mg, Cr, Zr, Mo, Gd, Ni, Pb, Ag, Y, La, Tb, Dy, B, Ga, Be, Ca, Ce, Pr, Eu, Ti, Cu, Na, Pd, Nd, Sm, Sc BOX 4 Composition of Fuel Obtained Through Pyroelectrochemical Regeneration of Spent Fuel from VVER-1000 or RBMK Reactors Left after regeneration: U 99.9% Pu 99.96% Am and Cm in approximately the same quantity per kg as in fuel prepared on the basis of spent fuel from BOR-60 reactors Standard purification coefficients for fission products: Ru-106 13 Ce-144 19 Sb-125 120 Eu-154 and -155 33 Cs-137 30,000 Obviously a substantial part of the fission products and minor actinides remains in the fuel to be reloaded into the active zone of the reactor.
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From page 192... ...
The technologies and procedures for primary processing of radioactive wastes formed during the pyrochemical regeneration of spent fuel are shown in Box 6. BOX 5 Sources of Radioactive Wastes Created During Pyroelectrochemical Regeneration of Spent Nuclear Fuel · Liquid wastes: soda solution (gamma and alpha nuclides suitable for under ground burial in liquid form)
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From page 193... ...
The fluoride gas technology for regenerating spent nuclear fuel is less ready for industrial application. Nevertheless, a certain amount of research has been completed with regard to the management of radioactive wastes created as a result of this process.
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From page 194... ...
T-950°C TABLE 4 Solid Technical Wastes and Products Waste Product Mass, kg Mn-54 Co-60 UO2-1 product after electrolysis of restored melt 0.489 < 4.4 < 1.6 UO2-2 product after electrolysis of acidified melt 1.510 0.3 0.5 PuO2 product after precipitation crystallization 0.504 2.2 0.1 Phosphate precipitate 0.442 24.8 1.3 Spent electrolyte 8.114 -- 0.1 Steamed salts 0.968 2.1 0.4 Sublimates 0.495 traces traces Pyrographite materials, filters, fuel rod casings 20 0.8 -
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From page 195... ...
1 · 1018 emitters/g 36 4 · 106 400 Amount of Wastes Cs-137 Leaching Rate Thermal Incorporated (percent) Over 7 Days, g/cm2/day Stability, °C Radiation Stability 100 1 · 106 850 5 · 108 grays 3040 3 · 106 1,000 (, )
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From page 196... ...
glass Pouring of aluminofluorophosphate( glass preparation of melt Glass and wastes wastes Induction of Phosphate Vitrification 1 Loading FIGURE
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From page 197... ...
All of these materials can be safely stored without any special preparation in stainless steel containers; however, for long-term controlled storage a technology has been developed for the preliminary smelting of solid wastes. Box 7 describes the process for preparing solid wastes with high specific activity and presents information on their fundamental properties.
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From page 198... ...
. · Radioactive wastes created as a result of pyroelectrochemical regeneration may be placed fairly easily in glass or ceramic forms suitable for permanent burial.
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