Determination of the fast fission yield of141Pr using neutron activation analysis |
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| Authors: | K K S Pillay R J Meyer R P Larsen |
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| Institution: | (1) Argonne National Laboratory Argonne, 60439 Illinois, (USA);(2) Present address: Western New York Nuclear Research Center, Inc., Power Drive, 14214 Buffalo, New York, (USA) |
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| Abstract: | A method is described for the determination of the fission yield of141Pr. This method was developed to determine the fast fission yield of141Pr in the Mark III loading (enriched uranium with about 2% zirconium) of the fast fission breeder reactor, EBR-1. The burnup
of the fuel sample was determined using the previously reported fission yield of137Cs. Praseodymium was separated from uranium, plutonium and other fission products by a combination of precipitation and ion
exchange stages. Thereafter,55Mn was added to serve as an internal flux monitor and praseodymium determined by neutron activation analysis. A precision
of ±2% was obtained.
Presented at the 15th Annual Meeting of the American Chemical Society, Miami Beach, Florida (USA), April 1967. |
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