ISO/DIS 6863
u
ISO/DIS 6863
84363

Status : Under development

en
Format Language
std 1 63 PDF
std 2 63 Paper
  • CHF63
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Abstract

This method applies to the preparation and validation of the spikes used for the measurement of the concentration of uranium and/or plutonium in input solutions of irradiated Magnox and light water reactor fuels (boiling water reactor or pressurized water reactor), in final products at spent-fuel reprocessing plants and in feed and products of MOX and uranium fuel fabrication by isotope dilution mass spectrometry (IDMS).

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General information

  •  : Under development
    : Close of voting [40.60]
  •  : 1
     : 14
  • ISO/TC 85/SC 5
    27.120.30 
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