Prototype fast reactors fuel reprocessing

Prototype fast reactors fuel reprocessing, 955 Prussian blue in cyclic water cleavage hydrogen and oxygen production, 525 electrode modification, 21 Pseudobactin, 678 animal infections, 679 Pseudocatalase... 

Figure 47 An outline flowsheet for the reprocessing of Prototype Fast Reactor fuel at Dounreay436...

To close the fast breeder reactor (FBR) fuel cycle, a fast reactor fuel cycle facility (FRFCF) has long been planned, with construction originally to begin in 2008 and operation to coincide with the need to reprocess the first prototype fast breeder reactor (PFBR) fuel. The PFBR and the next four FBRs to be commissioned by 2020 will use oxide fuel. After that, it is expected that metal fuel with higher breeding capability will be introduced and burn-up is intended to increase from 100 to 200 GWd H. 

At Dounray the Material Testing Reactor Fuel Reprocessing Plant has almost finished all MTR fuel. The Prototype Fast Reactor Reprocessing Plant is being reprocessing the remaining oxide fuel from PFR. 

Work at Dounreay site had begun in 1955. By 1979, the site was huge and employed some 2500 people. The site was divided between the fuel cycle area where used fuel was reprocessed, and the Prototype Fast Reactor (or PHi) itself which could generate enough electricity for a city. There was also a smaller fast reactor, the original Doumeay Fast Reactor (with its iconic golf ball containment building) that had shutdown in 1977. 

We recognise that there is continuing benefit to be secured from operation of the prototype fast reactor. We have therefore decided to fund the reactor until the end of the financial year 1993-94. This will enable operating experience to accumulate for a further five years. We have also decided to fund the reprocessing plant at Dounreay until 1996-97, to process spent fuel from the reactor. Our decisions will ensure continuing and substantial employment at Dounreay into the late 1990s. 

There are two breeder reactor fuel cycles. One involves the irradiation of U/ Pu oxide fuel with fast neutrons and is at the prototype stage of development. The other involves the irradiation of Th/ U oxide fuel with thermal neutrons and is at the experimental stage. Fuel from the U/ Pu cycle may be reprocessed using Purex technology adapted to accommodate the significant proportion of plutonium present in the fuel. Increased americium and neptunium levels will also arise compared with thermal reactor fuel. The Th/ U fuel may also be reprocessed using solvent extraction with TBP in the Thorex (Thorium Recovery by Extraction) process. In this case the extraction chemistry must also take account of the presence of Pa arising as shown in Scheme 2. 

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