Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor
The Generation IV International Forum has identified the Gas-Cooled Fast Reactor (GCFR) as one of the reactor concepts for future deployment. The GCFR targets sustainability, which is achieved by the use of a closed nuclear fuel cycle where only fission products are discharged to a repository; all H...
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| Main Authors: | , |
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| Format: | Article |
| Language: | English |
| Published: |
Wiley
2009-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2009/282365 |
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| Summary: | The Generation IV International Forum has identified the Gas-Cooled
Fast Reactor (GCFR) as one of the reactor concepts for future deployment. The GCFR targets sustainability, which is achieved by the use of a closed nuclear fuel cycle where only fission products are discharged to a repository; all Heavy Metal isotopes are to be recycled in the reactor. In this paper, an overview is presented of recent results obtained
in the study of the closed fuel cycle and the influence of the addition of
extra Minor Actinide (MA) isotopes from existing LWR stockpiles. In
the presented work, up to 10% of the fuel was homogeneously replaced
by an MA-mixture. The results are that addition of MA increases the
potential of obtaining a closed fuel cycle. Reactivity coefficients generally
decrease with increasing MA content. Addition of MA reduces
the reactivity swing and allows very long irradiation intervals up to 10% FIMA with a small reactivity swing. Multirecycling studies show that a 600 MWth GCFR can transmute the MA from several PWRs. By a
careful choice of the MA-fraction in the fuel, the reactivity of the fuel
can be tuned to obtain a preset multiplication factor at end of cycle.
Preliminary decay heat calculations show that the presence of MA in the
fuel significantly increases the decay heat for time periods relevant to
accidents (104–105 s after shutdown). The paper ends with some recommendations
for future research in this promising area of the nuclear fuel cycle. |
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| ISSN: | 1687-6075 1687-6083 |