Uncertainty quantification applied to the radiological characterization of radioactive waste

DSpace Repository

Show simple item record

dc.contributor.author ZAFFORA, Biagio
ensam.hal.laboratories
  6925 CERN [Genève]
  86289 Procédés et Ingénierie en Mécanique et Matériaux [Paris] [PIMM]
dc.contributor.author MAGISTRIS, M
ensam.hal.laboratories
  495918 European Organization for Nuclear Research [CERN]
dc.contributor.author SAPORTA, G
ensam.hal.laboratories
  300351 Conservatoire National des Arts et Métiers [CNAM] [CNAM]
dc.contributor.author CHEVALIER, Jean-Pierre
ensam.hal.laboratories
  300351 Conservatoire National des Arts et Métiers [CNAM] [CNAM]
  86289 Procédés et Ingénierie en Mécanique et Matériaux [Paris] [PIMM]
dc.date.accessioned 2018-01-05T14:08:52Z
dc.date.available 2018-03-01T01:42:29Z
dc.date.issued 2017
dc.date.submitted 2017-11-16T16:21:32Z
dc.identifier.uri http://hdl.handle.net/10985/12463
dc.description.abstract This paper describes the process adopted at the European Organization for Nuclear Research (CERN) to quantify uncertainties affecting the characterization of very-low-level radioactive waste. Radioactive waste is a by-product of the operation of high-energy particle accelerators. Radioactive waste must be characterized to ensure its safe disposal in final repositories. Characterizing radioactive waste means establishing the list of radionuclides together with their activities. The estimated activity levels are compared to the limits given by the national authority of the waste disposal. The quantification of the uncertainty affecting the concentration of the radionuclides is therefore essential to estimate the acceptability of the waste in the final repository but also to control the sorting, volume reduction and packaging phases of the characterization process. The characterization method consists of estimating the activity of produced radionuclides either by experimental methods or statistical approaches. The uncertainties are estimated using classical statistical methods and uncertainty propagation. A mixed multivariate random vector is built to generate random input parameters for the activity calculations. The random vector is a robust tool to account for the unknown radiological history of legacy waste. This analytical technique is also particularly useful to generate random chemical compositions of materials when the trace element concentrations are not available or cannot be measured. The methodology was validated using a waste population of legacy copper activated at CERN. The methodology introduced here represents a first approach for the uncertainty quantification (UQ) of the characterization process of waste produced at particle accelerators. en
dc.language.iso en
dc.publisher Elsevier
dc.rights Post-print
dc.subject Radioactive waste en
dc.subject Uncertainty quantification en
dc.subject Particle accelerator en
dc.subject Random vector en
dc.title Uncertainty quantification applied to the radiological characterization of radioactive waste en
ensam.hal.id hal-01676367 *
ensam.hal.status accept *
ensam.embargo.terms 2018-03-01
dc.identifier.doi 10.1016/j.apradiso.2017.06.001
dc.typdoc Articles dans des revues avec comité de lecture
dc.localisation Centre de Paris
dc.subject.hal Sciences de l'ingénieur: Matériaux
dc.subject.hal Sciences de l'ingénieur: Mécanique
ensam.workflow.submissionConsumer updateFiles *
ensam.audience Internationale
ensam.page 142-149
ensam.journal Applied Radiation and Isotopes
ensam.volume 127
ensam.peerReviewing Oui

Files in this item

 

This item appears in the following Collection(s)

Show simple item record

Search


Number of documents in SAM

  • 2890 references in SAM

Newsletter

My Account

Reporting Suite

Help