Preparation of higher-actinide burnup and cross section samples. [LMFBR]
A joint research program involving the United States and the United Kingdom was instigated about four years ago for the purpose of studying burnup of higher actinides using in-core irradiation in the fast reactor at Dounreay, Scotland. Simultaneously, determination of cross sections of a wide variety of higher actinide isotopes was proposed. Coincidental neutron flux and energy spectral measurements were to be made using vanadium encapsulated dosimetry materials in the immediate region of the burnup and cross section samples. The higher actinide samples chosen for the burnup study were /sup 241/Am and /sup 244/Cm in the forms of Am/sub 2/O/sub 3/, Cm/sub 2/O/sub 3/, and Am/sub 6/ Cm(RE)/sub 7/O/sub 21/, where (RE) represents a mixture of lanthanide sesquioxides. It is the purpose of this paper to describe technology development and its application in the preparation of the fuel specimens and the cross section specimens that are being used in this cooperative program.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6083803
- Report Number(s):
- CONF-811098-1; ON: DE82002877; TRN: 82-000400
- Resource Relation:
- Conference: International Nuclear Target Development Society conference, Rehovot, Israel, 19 Oct 1981
- Country of Publication:
- United States
- Language:
- English
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BURNUP
FUEL MANAGEMENT
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AMERICIUM 241
CURIUM 244
FUEL CYCLE
ISOTOPE RATIO
REACTOR OPERATION
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
AMERICIUM ISOTOPES
BREEDER REACTORS
CURIUM ISOTOPES
EPITHERMAL REACTORS
EVEN-EVEN NUCLEI
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FUEL ELEMENTS
HEAVY NUCLEI
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ODD-EVEN NUCLEI
OPERATION
RADIOISOTOPES
REACTOR COMPONENTS
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YEARS LIVING RADIOISOTOPES
210500* - Power Reactors
Breeding