Determination of PuO2% in power reactor mixed oxide fuel blends (0.4–44% PuO2) by neutron well co-incidence counting technique

Neutron Well Coincidence Counting has been explored as a non destructive assay technique for determining the percentage of PuO 2 in blended mixture of UO 2 and PuO 2 powders. The method has been applied to MOX blends having PuO 2 content varying from 0.4 to 44% for both thermal and fast reactors. Th...

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Bibliographic Details
Published in:Journal of radioanalytical and nuclear chemistry 2010-05, Vol.284 (2), p.451-455
Main Authors: Karande, A. P., Fulzele, A. K., Prakash, Amrit, Afzal, Md, Panakkal, J. P., Kamath, H. S.
Format: Article
Language:English
Subjects:
Blends
Chemistry
Chemistry and Materials Science
Counting
Diagnostic Radiology
Fuels
Hadrons
Heavy Ions
Inorganic Chemistry
MOX
Nuclear Chemistry
Nuclear Physics
Nuclear power generation
Nuclear reactor components
Nuclear reactors
Physical Chemistry
Polymer blends
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Summary:Neutron Well Coincidence Counting has been explored as a non destructive assay technique for determining the percentage of PuO 2 in blended mixture of UO 2 and PuO 2 powders. The method has been applied to MOX blends having PuO 2 content varying from 0.4 to 44% for both thermal and fast reactors. The use of Neutron Well Coincidence Counting technique is validated as a process control step for determining PuO 2 content in the fabrication of MOX fuel by comparing it with chemical analysis of sintered pellets. It has been used at Advanced Fuel fabrication Facility, Bhabha Atomic Research Centre, Tarapur during the manufacture of MOX fuel of various types for thermal and fast reactors.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-010-0497-5