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Kim, Daeji,Croudace, Ian W.,Warwick, Phillip E. Elsevier 2012 Journal of hazardous materials Vol.213 No.-
<P><B>Highlights</B></P><P>► Identification of variation in tritium loss rates in concrete samples. ► Quantification of variation in tritium loss rates under different storage conditions. ► Quantification of tritium cross-contamination rates for a range of matrix types. ► Storage strategies for routine waste characterisation involving tritium.</P> <P><B>Abstract</B></P><P>Large volumes of potentially tritium-contaminated waste materials are generated during nuclear decommissioning that require accurate characterisation prior to final waste sentencing. The practice of initially determining a radionuclide waste fingerprint for materials from an operational area is often used to save time and money but tritium cannot be included because of its tendency to be chemically mobile. This mobility demands a specific measurement for tritium and also poses a challenge in terms of sampling, storage and reliable analysis. This study shows that the extent of any tritium redistribution during storage will depend on its form or speciation and the physical conditions of storage. Any weakly or moderately bound tritium (e.g. adsorbed water, waters of hydration or crystallisation) may be variably lost at temperatures over the range 100–300°C whereas for more strongly bound tritium (e.g. chemically bound or held in mineral lattices) the liberation temperature can be delayed up to 800°C. For tritium that is weakly held the emanation behaviour at different temperatures becomes particularly important. The degree of <SUP>3</SUP>H loss and cross-contamination that can arise after sampling and before analysis can be reduced by appropriate storage. Storing samples in vapour tight containers at the point of sampling, the use of triple enclosures, segregating high activity samples and using a freezer all lead to good analytical practice.</P>
Validation of Radioanalytical Techniques for Nuclear Waste Characterisation
Warwick, Phillip E. Korean Radioactive Waste Society 2019 방사성폐기물학회지 Vol.17 No.4
Waste characterisation associated with nuclear site decommissioning relies on radiochemical analysis of a diverse range of sample types, requiring extensive validation of analytical techniques using matrix-matched materials. The absence of relevant reference materials has hindered robust method development and validation. The paper discusses how method validation in support of nuclear waste characterisation can be achieved without using reference materials. The key stages in an analytical procedure are evaluated and a multi-stage approach is proposed with the ultimate aim of determining an operational envelope for an analytical procedure.
Validation of Radioanalytical Techniques for Nuclear Waste Characterisation
Phillip E. Warwick 한국방사성폐기물학회 2019 방사성폐기물학회지 Vol.17 No.4
Waste characterisation associated with nuclear site decommissioning relies on radiochemical analysis of a diverse range of sample types, requiring extensive validation of analytical techniques using matrix-matched materials. The absence of relevant reference materials has hindered robust method development and validation. The paper discusses how method validation in support of nuclear waste characterisation can be achieved without using reference materials. The key stages in an analytical procedure are evaluated and a multi-stage approach is proposed with the ultimate aim of determining an operational envelope for an analytical procedure.