Methodology for measuring and evaluation of inventory in the waste chlore-36 graphite - CEA - Commissariat à l’énergie atomique et aux énergies alternatives Access content directly
Conference Papers Year : 2015

Methodology for measuring and evaluation of inventory in the waste chlore-36 graphite


Methodology for measuring and evaluating chlorine-36 inventory in the graphite waste. About 23,000 tons of irradiated graphite waste will be produced during the dismantling of the reactors of the UNGG sector of CEA and EDF. Therefore determining the content of radionuclides from these graphite waste is a necessity both for security reasons and to determine the best strategy for their management. In order to strengthen the data for the estimation of waste inventories, development of more and more precise and repeatable characterization methods associated with an activation modeling approach have been undertaken to refine over time inventories. These developments concern all areas which provide quantification in the laboratory, including the sampling in reactor, the methodology of homogenization and grinding of samples, and finally the analytical method. This presentation will focus on the development for the characterization of chlorine 36. Chlorine 36 is one of the long-lived radionuclides present in the graphite in low activity, but because of its mobile behavior in storage conditions it is sizing for the studies of impact of storage sites. This presentation will also show in a first part developments made for reliability measurements and in a second part the method developed for the assessment of inventory. This method, based on a calculation-measurement identification process is developed by EDF-CIDEN to assess the inventory of radionuclides as precisely as possible while ensuring an increase corresponding to a 2.5% of underestimation. This method accurately reflects the reality of the main phenomenon explaining the presence of radionuclides in a reactor, while incorporating the secondary effects which may alter this result such as the release of radionuclides or their precursors during the operation of the reactor.
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hal-02445727 , version 1 (20-01-2020)


  • HAL Id : hal-02445727 , version 1


B. Poncet, J. Comte. Methodology for measuring and evaluation of inventory in the waste chlore-36 graphite. CETAMA workshop on Sampling and Characterisation, November 2015, Montpellier, Oct 2015, Monpellier, France. ⟨hal-02445727⟩


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