10.2 Demonstration Study of an Accelerator-Driven Transmutation System with the Experimental Reactor

Fig. 10-3 Concept of the transmutation experiment reactor
This shows the nitride fuel subassembly and the tungsten target subassembly.

Fig. 10-4 Neutron energy spectrum determining the transmutation efficiency
It is apparent that the neutron spectrum, in which many neutrons concentrate around the peak, on the uranium nitride fuelled core in the experiment reactor can reproduce very well the one obtained in designing a commercial-type transmutation core.

Table 10-1 Characteristics of the nitride fuelled transmutation core

With an effective multiplication factor of about 0.93 (neutron multiplicity: 14), this system can achieve about 10% of the MA transmutation reaction ratio obtained in a commercial-size transmutation plant.


For the safe application of nuclear power, radioactive waste processing is one of the most important problems. In particular, the handling of Minor Actinide (MA) wastes such as neptunium and americium nuclides with very long half-lives of several thousand years to several million years is most difficult. As one of the major themes in the Neutron Science Project, JAERI performs a research and development on an accelerator-driven transmutation plant which effectively process these radioactive wastes. In the plant, MA wastes are used as fuel materials in a subcritical transmutation core and the chain reaction in the core is maintained by spallation neutrons generated in the target bombarded by a high energy proton beam from an accelerator. As a result, this plant can transmute the MA's and can supply the power necessary to operate its own accelerator by converting the MA's fission energy to electric power.
As a first step of the development, JAERI has carried out a conceptual design study of an experimental reactor to simulate the commercial-type transmutation plant loaded with MA fuels, in which several fuel handling difficulties are anticipated. At present it has been concluded that the newly proposed uranium nitride fueled core can achieve about 10% of the MA transmutation reaction ratios. In the design study, its core parameters are adjusted to give an effective neutron multiplication factor of about 0.93 (neutron multiplicity of 14). The concept of the experimental reactor is shown in Fig. 10-3 and the characteristics is given in Table 10-1. It is also found that the neutron spectrum in the experimental reactor can reproduce very well the one obtained in designing a commercial-type core as shown in Fig. 10-4. The design result has also given good performance in transmuting the long-lived fission products such as technetium and iodine, large amounts of which are also included in the spent fuel. The present study has given us a clear guideline to establish a method for designing a transmutation demonstration experiment system.


Reference
T. Sasa et al., Conceptual Design and Code Development for Accelerator-Driven Transmutation System, Proc. Int. Conf. on Future Nuclear System, Oct. 5-10, 1997, Yokohama, Japan, 435 (1997).

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