Euradwaste '08 - EU Bookshop - Europa
Euradwaste '08 - EU Bookshop - Europa Euradwaste '08 - EU Bookshop - Europa
Pu or M.A. by the time it is needed in the transmutation plants, without requiring strong peaks in the utilization of the reprocessing and fabrication plants. However, this will result in significant stocks of Pu and M.A. separated or in Pu/M.A. rich fuels fabricated in advance. The studies also show that reaching equilibrium composition is a very slow process and that reducing significantly the waste inventories in scenarios on reduction of nuclear power will require very long times, although regional cooperation might reduce this periods of time to the lifetime of the transmutation plants. - In addition, the transition scenarios have also shown the relevance of waiting till the appropriate technology is available. For example, the use of standard reprocessing technologies that will send all M.A. to the HLW glasses will not be acceptable in scenarios of reduction of the nuclear energy installed power, where the M.A. inventory reduction is one of the main objectives. If this was done, the inventory of M.A. immobilized in the glasses will limit the possible reduction on TRU mass to less than a factor 10 instead of the factor 100 reachable if the all the M.A. are transmuted before their storage. These considerations depend on the scenario, and this practice will be much more acceptable in the case of continuous or increased nuclear installed power. It must be noted that the benefits provided by P&T will not be obtained by free. Indeed if no optimization, development and special protections are implemented, the risk of proliferation (reduced from the final repository) will increase in the different steps of the fuel cycle. Similarly the integral dose to workers in advanced fuel cycles could be larger. In addition, as already pointed before, there will be more secondary low and intermediate level wastes from the new steps of the advanced fuel cycles. Finally, depending on their implementation, advanced fuel cycles might require an increase of the transports of radioactive material, and the operation of interim storages of different radioactive streams. All these aspects must be addressed thoroughly by detailed R&D programs. The PATEROS EU project has prepared a road-map for this R&D to be developed in the EU, to identify, develop and demonstrate the options and technologies that could allow obtaining the benefits of P&T without unacceptable risks or costs in the advanced fuel cycles. 7. Specific Rationales and Added Value of P&T for different scenarios of Nuclear Energy deployment 7.1 Added value of P&T for a sustainable energy production from Nuclear Fission The long term sustainability of nuclear energy requires from the technical point of view to maintain or improve the safety, efficiency and economical competitivity, in a continuous way, and to gain public acceptance and proliferation resistance from the social point of view. In addition, it has two technical conditions whose relevance increases with the envisaged duration of the nuclear power exploitation: to find sufficient fuel (at reasonable prices) and to be able to handle the continuous generation of radioactive wastes, particularly the HLW. P&T, in its generic sense, is a key element for these two conditions. The presently identified Uranium resources with the current technology and at the year 2004 nuclear electricity generation will be exhausted in 85 years [2]. This time can be reduced by the increase of Uranium demand foreseen from the increase of its deployment in emerging countries or can be increased if we take into account all the conventional resources. In total a range of 60 to 270 years is the present projection of U availability, with the second figure implying much higher U prices. P&T provides a new technology to the nuclear fuel cycle, based on of fast nuclear reactors and recycling of actinides that will make the presently identified Uranium resources worth 2500 years. In addition, this technology will turn the spent fuel from the present reactors from waste into valuable fuel, extending even further the possible exploitation period of nuclear fission energy. 134
Figure 4: Spent nuclear fuel (metric tons) as a function of time in the USA, for different prospective studies and scenarios. Countries committed to the continuous utilization of nuclear fission and with a large park of nuclear reactors would face a continuous production of radioactive wastes and a continuous grow in the number of repositories needed. For example, the amount of spent nuclear fuel accumulated in the USA as a function of time is displayed in Figure 4 for different evolutionary scenarios considered. As for Europe, the existing figures for year 2000 [8] indicate an accumulated amount of 37000 tons with additional 2500 tons of spent fuel being produced every year. Figure 5: Estimated number of geologic repositories in the USA, for the different scenarios of the cumulative spent fuel in 2100. The assessment of the number of geological repositories needed to accommodate the spent nuclear fuel in geological repositories varies with the different scenarios and solutions adopted for the fuel cycles and with the implemented radioactive waste and fuel management policies. As an example, Figure 5 provides an estimation of the number of repositories needed in year 2100 in the U.S.A., for different scenarios and corresponding amounts of cumulative spent nuclear fuel. The reference indicate that only one repository is need with P&T, whereas as much as 5-22 could be required with the direct disposal policy, or otherwise that a repository able to receive the spent fuel of 50 years of open cycle, could accept the HLW of advanced fuel cycles with P&T, corresponding to 250-1000 years. The reutilization of energy and the extension of the value of fuel resources from less than 100 years to several thousands can also be achieved by the simple closed fuel cycle with continuous recycling 135
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Pu or M.A. by the time it is needed in the transmutation plants, without requiring strong peaks<br />
in the utilization of the reprocessing and fabrication plants. However, this will result in significant<br />
stocks of Pu and M.A. separated or in Pu/M.A. rich fuels fabricated in advance. The<br />
studies also show that reaching equilibrium composition is a very slow process and that reducing<br />
significantly the waste inventories in scenarios on reduction of nuclear power will require<br />
very long times, although regional cooperation might reduce this periods of time to the lifetime<br />
of the transmutation plants.<br />
- In addition, the transition scenarios have also shown the relevance of waiting till the appropriate<br />
technology is available. For example, the use of standard reprocessing technologies that<br />
will send all M.A. to the HLW glasses will not be acceptable in scenarios of reduction of the<br />
nuclear energy installed power, where the M.A. inventory reduction is one of the main objectives.<br />
If this was done, the inventory of M.A. immobilized in the glasses will limit the possible<br />
reduction on TRU mass to less than a factor 10 instead of the factor 100 reachable if the all<br />
the M.A. are transmuted before their storage. These considerations depend on the scenario,<br />
and this practice will be much more acceptable in the case of continuous or increased nuclear<br />
installed power.<br />
It must be noted that the benefits provided by P&T will not be obtained by free. Indeed if no optimization,<br />
development and special protections are implemented, the risk of proliferation (reduced<br />
from the final repository) will increase in the different steps of the fuel cycle. Similarly the integral<br />
dose to workers in advanced fuel cycles could be larger. In addition, as already pointed before,<br />
there will be more secondary low and intermediate level wastes from the new steps of the advanced<br />
fuel cycles. Finally, depending on their implementation, advanced fuel cycles might require an increase<br />
of the transports of radioactive material, and the operation of interim storages of different<br />
radioactive streams.<br />
All these aspects must be addressed thoroughly by detailed R&D programs. The PATEROS <strong>EU</strong><br />
project has prepared a road-map for this R&D to be developed in the <strong>EU</strong>, to identify, develop and<br />
demonstrate the options and technologies that could allow obtaining the benefits of P&T without<br />
unacceptable risks or costs in the advanced fuel cycles.<br />
7. Specific Rationales and Added Value of P&T for different scenarios of Nuclear Energy<br />
deployment<br />
7.1 Added value of P&T for a sustainable energy production from Nuclear Fission<br />
The long term sustainability of nuclear energy requires from the technical point of view to maintain<br />
or improve the safety, efficiency and economical competitivity, in a continuous way, and to gain<br />
public acceptance and proliferation resistance from the social point of view. In addition, it has two<br />
technical conditions whose relevance increases with the envisaged duration of the nuclear power<br />
exploitation: to find sufficient fuel (at reasonable prices) and to be able to handle the continuous<br />
generation of radioactive wastes, particularly the HLW. P&T, in its generic sense, is a key element<br />
for these two conditions.<br />
The presently identified Uranium resources with the current technology and at the year 2004 nuclear<br />
electricity generation will be exhausted in 85 years [2]. This time can be reduced by the increase<br />
of Uranium demand foreseen from the increase of its deployment in emerging countries or<br />
can be increased if we take into account all the conventional resources. In total a range of 60 to 270<br />
years is the present projection of U availability, with the second figure implying much higher U<br />
prices. P&T provides a new technology to the nuclear fuel cycle, based on of fast nuclear reactors<br />
and recycling of actinides that will make the presently identified Uranium resources worth 2500<br />
years. In addition, this technology will turn the spent fuel from the present reactors from waste into<br />
valuable fuel, extending even further the possible exploitation period of nuclear fission energy.<br />
134