Abstract

Specifies an analytical method for determining the solubility in nitric acid of plutonium in whole pellets of unirradiated mixed oxide fuel (light water reactor fuels). The results provide information about the expected dissolution behaviour of irradiated pellets under industrial reprocessing conditions.


General information 

  • Status
     : Withdrawn
    Publication date
     : 1994-08
  • Edition
     : 1
    Number of pages
     : 3
  • Technical Committee
     : ISO/TC 85/SC 5 Nuclear installations, processes and technologies
  • ICS
     :
    27.120.30 Fissile materials and nuclear fuel technology

Life cycle

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