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RRFM 2009 Transactions - European Nuclear Society

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2. Advanced nuclear fuel cycles<br />

The rationale for the research and technology development programs in the field of ADS must<br />

be seen in the context of the efforts to establish innovative nuclear fuel cycles including<br />

partitioning and transmutation (P&T).<br />

Presently, industrial maturity can be claimed for two fuel cycle strategies, i.e. the "Once<br />

Through Fuel Cycle" (OTC), and the "Reprocessing Fuel Cycle" (RFC) in which plutonium and<br />

very limited uranium quantities are being recycled. It is helpful to recall some key data that set<br />

the stage for any fuel cycle (waste management) discussion: worldwide, the annual spent fuel<br />

discharge is in the range of 10’500 – 11’000 t heavy-metal (HM), while the industrial<br />

reprocessing capacity amounts to ~5’000 t HM [3]. Hence, less than ½ of the discharged spent<br />

fuel can be processed. Worldwide, the cumulative inventory of stored spent fuel is estimated to<br />

be ~130’000 t HM, and the amount of reprocessed spent fuel is estimated to be ~70’000 t HM.<br />

The latter inventory has been transformed into high-level waste (HLW) and spent light water<br />

reactor (LWR) mixed uranium-plutonium oxide (MOX) fuel. Considering the relatively low<br />

uranium ore prices, this situation is expected to continue over the next few decades (the<br />

cumulative inventory of stored spent fuel could reach 192’000 t HM by 2010). Therefore, it is<br />

likely that the need for repository space will increase accordingly. Taking Yucca Mountain<br />

(63’000 t HM capacity) as reference repository, the present worldwide inventories would require<br />

two repositories for the spent fuel, and one for the HLW. For the USA alone (OTC strategy),<br />

assuming a life time extension of the present nuclear reactors to 60 years, and no new<br />

reactors, the capacity of Yucca Mountain will be exceeded by ~2050. Given the strong public<br />

opposition to the construction of geologic repositories, it is understandable that over the last<br />

decade or so, in various countries and at an international level, more and more studies have<br />

been carried out on advanced and innovative waste management strategies aiming at reducing<br />

the amount of long-lived radioactive waste through transmutation in fission reactors or ADS. In<br />

several IAEA Member States, P&T is being revisited with the goal of reassessing its merits and<br />

investigating new approaches that could be followed in implementing this innovative fuel cycle<br />

and waste management option.<br />

3. Status of ADS research and technology development<br />

P&T is a complex technology that implies the availability of advanced reprocessing plants,<br />

facilities for fuel fabrication of transuranics (TRUs), and irradiation facilities beyond the<br />

presently existing nuclear reactors. For the major part, partitioning consists in extending the<br />

current reprocessing techniques: in addition to uranium, plutonium and 129 I, also minor actinides<br />

(neptunium, americium and curium), and, possibly, also long-lived fission products ( 99 Tc, 93 Zr,<br />

135 Cs, 107 Pd and 79 Se) would be extracted from the liquid high level waste. This technology,<br />

could, to a certain extend, be extrapolated on the basis of decades-long industrial experience in<br />

Europe and Japan. Transmutation, on the other hand, requires fully new fuel fabrication plants<br />

and irradiation technologies and their implementation on an industrial scale. The use of existing<br />

nuclear reactors as transmutation devices results in modest incineration and transmutation<br />

yields, and, more importantly, is limited by both safety and operational considerations.<br />

Therefore, new concepts, i.e. dedicated fast reactors, and sub-critical systems (ADS and even<br />

fusion/fission hybrids) have been proposed as incineration/transmutation devices.<br />

ADS rely on the availability of a hard neutron source produced by the spallation process<br />

induced by a high-energy proton beam impinging on a heavy nuclide target. While ADS present<br />

an attractive potential, various specific economics and technological issues remain to be solved<br />

(e.g. capital costs, additional energy consumption, accelerator reliability, various physics and<br />

material science issues linked, e.g. to nuclear data, fuel performance, heavy liquid thermal<br />

hydraulics, etc).<br />

The assessment of the potential of the ADS technology must consider the fact that the<br />

spallation neutron source is much less effective than the fission one. Basic physics<br />

considerations comparing spallation and fission neutron sources lead to the conclusion that<br />

transforming the energy of one fission event (which yields roughly 200 MeV of energy and 3<br />

hard neutrons) into spallation results in approximately 20 MeV of energy and, in an optimum<br />

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