Assay data of spent nuclear fuel: the lab-work behind the numbers

Abstract

Computational modelling for spent nuclear fuel (SNF) characterization is already widely used and continuously further developed for a plethora of safety related applications and licensing issues in SNF management. An essential step in the development of these methodologies is the validation: the demonstration that the SNF elemental and isotopic composition is sufficiently accurately predicted by the code calculations. This validation step requires experimentally measured nuclide concentrations in SNF, together with an estimation of related uncertainties. The SFCOMPO 2.0 database of OECD/NEA is a database of such publicly available assay data of SNF. A basic understanding of all analytical steps that finally result in assay data of SNF is important for modelers when assessing the “fit-for-validation” requirement of an experimental dataset. The aim of this article is to explain users of such datasets the complex analytical pathway towards assay data. Points of attention, challenges and pitfalls all along the analytical pathway will be discussed, from sampling, dissolution procedures, necessary dilutions and separations, available analytical techniques, some related uncertainties, up to reporting of the results.

An isotope dilution mass spectrometry overview: tips and applications for the measurement of radionuclides

“…The irradiated sample rst has to be brought into solution, before spiking can occur. Dissolution of spent fuels for analysis is detailed elsewhere, [216][217][218][219][220][221] but in general terms an irradiated fuel is oen dissolved quantitatively by heating (under reux) under strong acidic conditions over several days inside a shielded hot cell. Only then can spikes be added to an aliquot of the dissolved sample, but crucially before any separations are started.…”

“…Separations of lanthanides and actinides are discussed elsewhere. [31][32][33]58,[222][223][224][225][226][227][228] Van Winckel et al 220 provide a useful summary of the situations in which off-line and on-line separations are used for spent nuclear fuels.…”