journal article·2010-07

Nuclide analysis in high burnup fuel samples irradiated in Vandellós 2

H.U. Zwicky, J. Low, M. Granfors, C. Alejano, J.M. Conde, C. Casado, J. Sabater, M. Lloret, M. Quecedo, J.A. Gago

Journal of Nuclear Materials· Volume 402· Issue 1
Publisher page

Abstract

Abstract In the framework of a high burnup fuel demonstration programme, rods with an enrichment of 4.5% 235 U were operated to a rod average burnup of about 70 MWd/kgU in the Spanish Vandellos 2 pressurised water reactor. The rods were sent to hot cells and used for different research projects. This paper describes the isotopic composition measurements performed on samples of those rods, and the analysis of the measurement results based on comparison against calculated values. The fraction and composition of fission gases released to the rod free volume was determined for two of the rods. About 8% of Kr and Xe produced by fission were released. From the isotopic composition of the gases, it could be concluded that the gases were not preferentially released from the peripheral part of the fuel column. Local burnup and isotopic content of gamma emitting nuclides were determined by quantitatively evaluating axial gamma scans of the full rods. Nine samples were cut at different axial levels from three of the rods and analysed in two campaigns. More than 50 isotopes of 16 different elements were assessed, most of them by Inductively Coupled Plasma Mass Spectrometry after separation with High Performance Liquid Chromatography. In general, these over 400 data points gave a consistent picture of the isotopic content of irradiated fuel as a function of burnup. Only in a few cases, the analysis provided unexpected results that seem to be wrong, in most cases due to unidentified reasons. Sample burnup analysis was performed by comparing experimental isotopic abundances of uranium and plutonium composition as well as neodymium isotopic concentrations with corresponding CASMO based data. The results were in agreement with values derived independently from gamma scanning and from core design data and plant operating records. Measured isotope abundances were finally assessed using the industry standard SAS2H sequence of the SCALE code system. This exercise showed good agreement between measured and calculated values for most of the analysed isotopes, similar to those reported previously for lower burnup ranges. Thus, it could be concluded, that SAS2H results for high burnup samples are not subject to higher uncertainty and/or different biases than for lower burnup samples, and that the different isotopic experimental measurement methods provide accurate results with acceptable precision.
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Research context

OpenAlex topics: Radioactive contamination and transfer · Isotope Analysis in Ecology · Nuclear Physics and Applications

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References (14)

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