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Journal of Radioanalytical and Nuclear Chemistry

, Volume 277, Issue 2, pp 419–428 | Cite as

Application of neutron well coincidence counting for plutonium determination in mixed oxide fuel fabrication plant

  • Pradeep Kumar
  • K. L. Ramakumar
Article

Abstract

Mixed oxide (MOX) fuel is an alternative to conventional enriched uranium oxide fuel in thermal reactors. Indian interest in plutonium recycle in thermal reactors is primarily due to the need to develop alternative indigenous fuel for two boiling water reactors (BWR) at Tarapur, which are designed to use imported light enriched uranium fuel. A few MOX assemblies have been fabricated and loaded into the reactors. Neutron well coincidence counting (NWCC) system has been successfully employed to check the enrichments of PuO2 in MOX blends. NWCC has also been successfully applied in developing dry recycling process of clean rejected oxide (CRO) and dirty rejected oxide (DRO).

Keywords

Plutonium Thermal Ionization Mass Spectrometry Spontaneous Fission Coincidence Counting Fast Breeder Test Reactor 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Springer Science+Business Media, LLC. 2008

Authors and Affiliations

  1. 1.Radioanalytical Chemistry Section, Radiochemistry and Isotope GroupBhabha Atomic Research CentreTrombay, MumbaiIndia

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