Laura Aldave de las Heras (original) (raw)
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Papers by Laura Aldave de las Heras
J. Anal. At. Spectrom., 2002
Applied Radiation and Isotopes, 2006
The National Institute of Standards and Technology (NIST) Standard Reference Material (SRM) for s... more The National Institute of Standards and Technology (NIST) Standard Reference Material (SRM) for seaweed was developed through an interlaboratory comparison with 24 participants from 16 countries. After evaluating different techniques to calculate certified values for the radionuclides, the median method was found to be the most representative technique. The certified values were provided for 13 radionuclides and information values were given for 15 more radionuclides. Results for the natural decay series showed disequilibrium in both the uranium and thorium series.
Frontiers in Energy Research, Jul 5, 2023
Computational modelling for spent nuclear fuel (SNF) characterization is already widely used and ... more 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.
Safety of Nuclear Waste Disposal, 2021
EPJ Nuclear Sciences & Technologies
The H2020 EU-funded SHARE project (Stakeholders- based Analysis of REsearch for Decommissioning) ... more The H2020 EU-funded SHARE project (Stakeholders- based Analysis of REsearch for Decommissioning) is a forerunner to the establishment of a framework for collaboration on research activities related to the decommissioning of nuclear facilities. SHARE aimed to provide an inclusive roadmap for decommissioning research, in both technical and non-technical areas, in the EU and abroad, to enable stakeholders to improve jointly safety, reduce costs and minimise environmental impact. SHARE has been built on a consultation process considering the needs and perspectives of different stakeholders all across the decommissioning value chain. The project also considered existing and emerging innovative technologies solutions as well as the international best practices in the field of decommissioning. After a three-year process, the project provides a Strategic Research Agenda and a Roadmap built on the participation of the international Stakeholder community in a multi-step process including a qu...
Proceedings of the National Academy of Sciences
The precise and accurate determination of the radionuclide inventory in radioactive waste streams... more The precise and accurate determination of the radionuclide inventory in radioactive waste streams, including those generated during nuclear decommissioning, is a key aspect in establishing the best-suited nuclear waste management and disposal options. Radiocarbon ( 14 C ) is playing a crucial role in this scenario because it is one of the so-called difficult to measure isotopes; currently, 14 C analysis requires complex systems, such as accelerator mass spectrometry (AMS) or liquid scintillation counting (LSC). AMS has an outstanding limit of detection, but only a few facilities are available worldwide; LSC, which can have similar performance, is more widespread, but sample preparation can be nontrivial. In this paper, we demonstrate that the laser-based saturated-absorption cavity ring-down (SCAR) spectroscopic technique has several distinct advantages and represents a mature and accurate alternative for 14 C content determination in nuclear waste. As a proof-of-principle experimen...
EPJ Nuclear Sciences & Technologies
Nuclear metrology is an essential aspect to consider for further improvements of the initial char... more Nuclear metrology is an essential aspect to consider for further improvements of the initial characterization of sites under decommissioning. The H2020 Euratom project INSIDER in June 2017 aims at improving the management of contaminated materials arising from decommissioning and dismantling (D&D) operations by proposing an integrated methodology for radiological characterization. This methodology is based on advanced statistical processing and modelling, coupled with adapted or innovative measurement methods. A metrological approach supports the qualification of this integrated methodology with a concrete application to real projects representative of the use cases identified in the project. Assessment of the outcomes will be used for providing recommendations and guidance resulting in pre-standardization texts.
EPJ Nuclear Sciences & Technologies
Molecules
To reduce uncertainties in determining the source term and evolving condition of spent nuclear fu... more To reduce uncertainties in determining the source term and evolving condition of spent nuclear fuel is fundamental to the safety assessment. ß-emitting nuclides pose a challenging task for reliable, quantitative determination because both radiometric and mass spectrometric methodologies require prior chemical purification for the removal of interfering activity and isobars, respectively. A method for the determination of 90Sr at trace levels in nuclear spent fuel leachate samples without sophisticated and time-consuming procedures has been established. The analytical approach uses a commercially available automated pre-concentration device (SeaFAST) coupled to an ICP-DRC-MS. The method shows good performances with regard to reproducibility, precision, and LOD reducing the total time of analysis for each sample to 12.5 min. The comparison between the developed method and the classical radiochemical method shows a good agreement when taking into account the associated uncertainties.
Journal of Visualized Experiments
A quick, automated and portable system for the separation and determination of radiostrontium in ... more A quick, automated and portable system for the separation and determination of radiostrontium in aqueous samples, using Sr-resin and multi sequential flow injection analysis, has been developed. The concentrations of radioactive strontium were determined by flow scintillation counting, allowing for on-line and also on-site determination. The proposed system can determine radioactive strontium at industrial relevant levels without further modification using overall analysis time of less than 10 min per aqueous sample. The limit of the detection is 320 fg•g-1 (1.7 Bq/g).
Journal of Nuclear Science and Technology
Journal of Radioanalytical and Nuclear Chemistry
A LabVIEW Ò-based software for the control of the fully automated multi-sequential flow injection... more A LabVIEW Ò-based software for the control of the fully automated multi-sequential flow injection analysis Lab-on-Valve (MSFIA-LOV) platform AutoRAD performing radiochemical analysis is described. The analytical platform interfaces an Arduino Ò-based device triggering multiple detectors providing a flexible and fit for purpose choice of detection systems. The different analytical devices are interfaced to the PC running LabVIEW Ò VI software using USB and RS232 interfaces, both for sending commands and receiving confirmation or error responses. The AUTORAD platform has been successfully applied for the chemical separation and determination of Sr, an important fission product pertinent to nuclear waste.
An overview is given of the current state of the art for the determination of radionuclide traces... more An overview is given of the current state of the art for the determination of radionuclide traces in the environment and the separation of fission products and actinides in nuclear samples by techniques like flow-injection (FI)/sequential injection analysis (SIA) and chromatography hyphenated to inductively coupled plasma mass spectrometry (ICP-MS).
Fresenius' journal of analytical chemistry, 2000
The quantitative determination of trace elements in nuclear samples by GDMS and ICP-MS is present... more The quantitative determination of trace elements in nuclear samples by GDMS and ICP-MS is presented and compared. Spectral interferences, matrix effects, detection limits, precision and accuracy are discussed. Results for selected samples demonstrated that both techniques are complementary. The use of a multi-standard solution provides the most accurate results in ICP-MS, whereas in GDMS this is achieved by relative sensitivity factors (RSF) matrix matched. Nevertheless, the use of standard RSF allows a fast screening.
Uranium in the Aquatic Environment, 2002
Hyphenated techniques for speciation of Uranium and other actinides Maria Betti, Laura Aldave de ... more Hyphenated techniques for speciation of Uranium and other actinides Maria Betti, Laura Aldave de las Heras, Lorenzo Perna, Fabio Bocci, Tania Huber European Commission, Joint Research Centre, Institute for Transuranium Ele-ments, PO Box 2340, 76125 ... 1986, Knight et al ...
Microchemical Journal, 2000
The depth distribution of B and Li have been studied in ZrO layers by GDMS. Zr alloy has been cor... more The depth distribution of B and Li have been studied in ZrO layers by GDMS. Zr alloy has been corroded to 2 ZrO in an autoclave in solutions containing Li and B. Samples were collected at different reaction times and 2 analyzed. The GDMS crater depth and the sputter rate could be determined by profilometry for the discharge conditions used. In the analyzed samples three zones could be identified: oxide, interface and zircaloy. The concentration of Li and B was followed in each of the three zones.
J. Anal. At. Spectrom., 2002
Applied Radiation and Isotopes, 2006
The National Institute of Standards and Technology (NIST) Standard Reference Material (SRM) for s... more The National Institute of Standards and Technology (NIST) Standard Reference Material (SRM) for seaweed was developed through an interlaboratory comparison with 24 participants from 16 countries. After evaluating different techniques to calculate certified values for the radionuclides, the median method was found to be the most representative technique. The certified values were provided for 13 radionuclides and information values were given for 15 more radionuclides. Results for the natural decay series showed disequilibrium in both the uranium and thorium series.
Frontiers in Energy Research, Jul 5, 2023
Computational modelling for spent nuclear fuel (SNF) characterization is already widely used and ... more 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.
Safety of Nuclear Waste Disposal, 2021
EPJ Nuclear Sciences & Technologies
The H2020 EU-funded SHARE project (Stakeholders- based Analysis of REsearch for Decommissioning) ... more The H2020 EU-funded SHARE project (Stakeholders- based Analysis of REsearch for Decommissioning) is a forerunner to the establishment of a framework for collaboration on research activities related to the decommissioning of nuclear facilities. SHARE aimed to provide an inclusive roadmap for decommissioning research, in both technical and non-technical areas, in the EU and abroad, to enable stakeholders to improve jointly safety, reduce costs and minimise environmental impact. SHARE has been built on a consultation process considering the needs and perspectives of different stakeholders all across the decommissioning value chain. The project also considered existing and emerging innovative technologies solutions as well as the international best practices in the field of decommissioning. After a three-year process, the project provides a Strategic Research Agenda and a Roadmap built on the participation of the international Stakeholder community in a multi-step process including a qu...
Proceedings of the National Academy of Sciences
The precise and accurate determination of the radionuclide inventory in radioactive waste streams... more The precise and accurate determination of the radionuclide inventory in radioactive waste streams, including those generated during nuclear decommissioning, is a key aspect in establishing the best-suited nuclear waste management and disposal options. Radiocarbon ( 14 C ) is playing a crucial role in this scenario because it is one of the so-called difficult to measure isotopes; currently, 14 C analysis requires complex systems, such as accelerator mass spectrometry (AMS) or liquid scintillation counting (LSC). AMS has an outstanding limit of detection, but only a few facilities are available worldwide; LSC, which can have similar performance, is more widespread, but sample preparation can be nontrivial. In this paper, we demonstrate that the laser-based saturated-absorption cavity ring-down (SCAR) spectroscopic technique has several distinct advantages and represents a mature and accurate alternative for 14 C content determination in nuclear waste. As a proof-of-principle experimen...
EPJ Nuclear Sciences & Technologies
Nuclear metrology is an essential aspect to consider for further improvements of the initial char... more Nuclear metrology is an essential aspect to consider for further improvements of the initial characterization of sites under decommissioning. The H2020 Euratom project INSIDER in June 2017 aims at improving the management of contaminated materials arising from decommissioning and dismantling (D&D) operations by proposing an integrated methodology for radiological characterization. This methodology is based on advanced statistical processing and modelling, coupled with adapted or innovative measurement methods. A metrological approach supports the qualification of this integrated methodology with a concrete application to real projects representative of the use cases identified in the project. Assessment of the outcomes will be used for providing recommendations and guidance resulting in pre-standardization texts.
EPJ Nuclear Sciences & Technologies
Molecules
To reduce uncertainties in determining the source term and evolving condition of spent nuclear fu... more To reduce uncertainties in determining the source term and evolving condition of spent nuclear fuel is fundamental to the safety assessment. ß-emitting nuclides pose a challenging task for reliable, quantitative determination because both radiometric and mass spectrometric methodologies require prior chemical purification for the removal of interfering activity and isobars, respectively. A method for the determination of 90Sr at trace levels in nuclear spent fuel leachate samples without sophisticated and time-consuming procedures has been established. The analytical approach uses a commercially available automated pre-concentration device (SeaFAST) coupled to an ICP-DRC-MS. The method shows good performances with regard to reproducibility, precision, and LOD reducing the total time of analysis for each sample to 12.5 min. The comparison between the developed method and the classical radiochemical method shows a good agreement when taking into account the associated uncertainties.
Journal of Visualized Experiments
A quick, automated and portable system for the separation and determination of radiostrontium in ... more A quick, automated and portable system for the separation and determination of radiostrontium in aqueous samples, using Sr-resin and multi sequential flow injection analysis, has been developed. The concentrations of radioactive strontium were determined by flow scintillation counting, allowing for on-line and also on-site determination. The proposed system can determine radioactive strontium at industrial relevant levels without further modification using overall analysis time of less than 10 min per aqueous sample. The limit of the detection is 320 fg•g-1 (1.7 Bq/g).
Journal of Nuclear Science and Technology
Journal of Radioanalytical and Nuclear Chemistry
A LabVIEW Ò-based software for the control of the fully automated multi-sequential flow injection... more A LabVIEW Ò-based software for the control of the fully automated multi-sequential flow injection analysis Lab-on-Valve (MSFIA-LOV) platform AutoRAD performing radiochemical analysis is described. The analytical platform interfaces an Arduino Ò-based device triggering multiple detectors providing a flexible and fit for purpose choice of detection systems. The different analytical devices are interfaced to the PC running LabVIEW Ò VI software using USB and RS232 interfaces, both for sending commands and receiving confirmation or error responses. The AUTORAD platform has been successfully applied for the chemical separation and determination of Sr, an important fission product pertinent to nuclear waste.
An overview is given of the current state of the art for the determination of radionuclide traces... more An overview is given of the current state of the art for the determination of radionuclide traces in the environment and the separation of fission products and actinides in nuclear samples by techniques like flow-injection (FI)/sequential injection analysis (SIA) and chromatography hyphenated to inductively coupled plasma mass spectrometry (ICP-MS).
Fresenius' journal of analytical chemistry, 2000
The quantitative determination of trace elements in nuclear samples by GDMS and ICP-MS is present... more The quantitative determination of trace elements in nuclear samples by GDMS and ICP-MS is presented and compared. Spectral interferences, matrix effects, detection limits, precision and accuracy are discussed. Results for selected samples demonstrated that both techniques are complementary. The use of a multi-standard solution provides the most accurate results in ICP-MS, whereas in GDMS this is achieved by relative sensitivity factors (RSF) matrix matched. Nevertheless, the use of standard RSF allows a fast screening.
Uranium in the Aquatic Environment, 2002
Hyphenated techniques for speciation of Uranium and other actinides Maria Betti, Laura Aldave de ... more Hyphenated techniques for speciation of Uranium and other actinides Maria Betti, Laura Aldave de las Heras, Lorenzo Perna, Fabio Bocci, Tania Huber European Commission, Joint Research Centre, Institute for Transuranium Ele-ments, PO Box 2340, 76125 ... 1986, Knight et al ...
Microchemical Journal, 2000
The depth distribution of B and Li have been studied in ZrO layers by GDMS. Zr alloy has been cor... more The depth distribution of B and Li have been studied in ZrO layers by GDMS. Zr alloy has been corroded to 2 ZrO in an autoclave in solutions containing Li and B. Samples were collected at different reaction times and 2 analyzed. The GDMS crater depth and the sputter rate could be determined by profilometry for the discharge conditions used. In the analyzed samples three zones could be identified: oxide, interface and zircaloy. The concentration of Li and B was followed in each of the three zones.