Abstract
ThO 2–PuO 2 mixed oxide (MOX) experimental fuel pins have been fabricated at Bhabha Atomic Research Centre, for irradiation experiments as a part of an advanced fuel development programme. During the quality control of fuel pellets, the homogeneous distribution of the fissile plutonium in them has been ascertained using alpha autoradiography and gamma autoradiography techniques. The quantitative estimation of the plutonium-rich regions of the pellets has been carried out by optical microdensitometry and digital image analysis. This paper discusses the implementation of the techniques and presents a few typical results.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
