Journal articles: 'H2020 Euratom'

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Herranz, Luis E., Gonzalo Jiménez, and Francesco S. Nitti. "Towards an optimized management of accidents." EPJ Nuclear Sciences & Technologies 8 (2022): 43. http://dx.doi.org/10.1051/epjn/2022019.

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Nuclear safety has been one of the main research domains in EURATOM programs for decades, and accident prevention and mitigation have drawn much of the attention paid over the years to this framework. In the essence of this interest are designs of reliable systems, accurate methods to estimate risk, and a permanent search for optimizing accident management. This is the focus of PIACE, MUSA, and AMHYCO projects. A fully passive system for decay heat removal in off-nominal conditions based on the concept of isolation condenser is the subject of PIACE. A harmonized approach for analyzing uncertainties and sensitivities associated with severe accidents, particularly with the source term to the environment, is the final aim of MUSA. And finally, AMHYCO is exploring the potential for enhancing the management of combustible gas risk. Despite the project’s diversity, they all will converge on the same outcome: an optimization of nuclear safety from better safety systems, risk estimating methods, and in-accident guidelines. These projects have received funding from the H2020 EURATOM research and training program under grant agreements 847715 (PIACE), 847441 (MUSA), and 945057 (AMHYCO).

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Luis, E. Herranz, Jimenez Gonzalo, and S. Nitti Francesco. "Towards an optimized management of accidents." EPJ Nuclear Sci. Technol. 8, Euratom Research and Training in 2022: challenges, achievements and future perspective (2022): 11. https://doi.org/10.1051/epjn/2022019.

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Abstract. Nuclear safety has been one of the main research domains in EURATOM programs for decades, and accident prevention and mitigation have drawn much of the attention paid over the years to this framework. In the essence of this interest are designs of reliable systems, accurate methods to estimate risk, and a permanent search for optimizing accident management. This is the focus of PIACE, MUSA, and AMHYCO projects. A fully passive system for decay heat removal in off-nominal conditions based on the concept of isolation condenser is the subject of PIACE. A harmonized approach for analyzing uncertainties and sensitivities associated with severe accidents, particularly with the source term to the environment, is the final aim of MUSA. And finally, AMHYCO is exploring the potential for enhancing the management of combustible gas risk. Despite the project's diversity, they all will converge on the same outcome: an optimization of nuclear safety from better safety systems, risk estimating methods, and in-accident guidelines. These projects have received funding from the H2020 EURATOM research and training program under grant agreements 847715 (PIACE), 847441 (MUSA), and 945057 (AMHYCO).

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Roudil, Danièle, Marielle Crozet, Sébastien Picart, et al. "Metrology applications to D&D issues: issues at stake for INSIDER European project." EPJ Nuclear Sciences & Technologies 6 (2020): 17. http://dx.doi.org/10.1051/epjn/2019052.

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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.

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Finocchiaro, Paolo, Luigi Cosentino, Fabio Longhitano, et al. "Field tests of the MICADO monitoring detectors in real radwaste storages." EPJ Web of Conferences 288 (2023): 06006. http://dx.doi.org/10.1051/epjconf/202328806006.

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In the framework of the MICADO project, funded by Euratom H2020 program, a system of gamma ray and neutron counters was developed. These counters are meant to be deployed as a monitoring grid around radwaste drums in low and/or intermediate waste storage sites, even though they could be usefully employed also for high level waste. A prototype of the MICADO gamma and neutron monitoring grid was installed and tested around real radwaste drums in two storage sites on the ORANO and NUCLECO premises, at La Hague and Casaccia respectively. A modular support structure, was assembled in four units in order to accommodate four radwaste drums. Each support unit hosted four gamma ray counters and four neutron counters. In both cases the units were installed around four radwaste drums also containing small or tiny quantities of actinides, and data were acquired. The results are quite promising as the system behaved as expected from previous tests and from the nominal radiological info about the drums.

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Herranz, Luis E., Gonzalo Jiménez, and Teemu Kärkelä. "Enhancing severe accident management through research." EPJ Nuclear Sciences & Technologies 11 (2025): 10. https://doi.org/10.1051/epjn/2025004.

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After the Fukushima Daiichi accident, a new wave of research projects aiming at enhancing severe accident (SA) management was launched under different international frameworks. This was the case of MUSA (Management and Uncertainties of Severe Accidents), AMHYCO (Towards and enhanced Accident Management of the H2 and CO combustion risk) and SOCRATES (Assessment of liquid Source Term for accidental post management phase), which under the frame of H2020 and HEUROPE EURATOM were devised to optimize different aspects of Severe Accident management. MUSA explored how bringing uncertainties quantification in the Severe Accident analysis might provide sounder insights into effects and timing of accident management actions. AMHYCO brought new insights into combustion risk management, particularly during the ex-vessel phase of the accident, by combining in a selective manner different analytical approaches and data on recombination and combustion of gas mixtures (i.e., H2/CO/air/steam). SOCRATES is hitting accident management related to liquid source terms, with emphasis in the long-run of the accident. This paper describes the major outcomes of the projects and outlines what should come next for an efficient application of the insights gained in the accident management.

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Di Ronco, Andrea, Francesca Giacobbo, Guglielmo Lomonaco, Stefano Lorenzi, Xiang Wang, and Antonio Cammi. "Preliminary Analysis and Design of the Energy Conversion System for the Molten Salt Fast Reactor." Sustainability 12, no. 24 (2020): 10497. http://dx.doi.org/10.3390/su122410497.

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The unique design features of the molten salt fast reactor (MSFR) should enable higher coolant temperatures than in conventional water reactors, with a significant improvement in the achievable thermodynamic performance. The use of a molten salt as both fuel and coolant, however, poses several advanced heat transfer challenges, such as the design of innovative heat exchangers and energy conversion systems. In this work, we address a preliminary but quantitative analysis of the energy conversion system for the MSFR, based on reference design data from the SAMOFAR H2020-EURATOM project. We consider three main technologies, i.e., the supercritical steam cycle, the closed helium cycle and the helium/steam combined cycle. Preliminary design results are presented for each technology, based on a simplified modelling approach. The considered cycles show promising efficiency improvements, with the best performance being proven by the supercritical steam cycle. The analysis also highlights the critical issue related to the risk of freezing of the molten salts within the secondary heat exchangers, due to the low inlet temperatures of the working fluids. Results show potential incompatibility between the freezing point of molten salts and the temperatures typical of steam cycles, while helium cycles offer the best chances of freezing avoidance. The combined cycle promises intermediate performance in terms of thermodynamic efficiency and thermal compatibility with molten salts comparable with closed helium cycles.

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Cagnac, Albannie, Denis Verrier, and Vladislav Pištora. "Codes and methods improvements for safety assessment and LTO: varied approaches." EPJ Nuclear Sciences & Technologies 9 (2023): 20. http://dx.doi.org/10.1051/epjn/2023001.

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Nuclear safety has always been at the heart of the concerns of nuclear power plant operators and developers, as well as of various nuclear research organizations and regulatory authorities. Over the last decades, all these nuclear actors have developed and integrated a large number of calculation codes and other tools into their safety work. From the system approach to the local understanding of a phenomenon on a given component, from neutronics to operation optimization for long-term operation, these methods and codes have been constantly evolving since their appearance, in order to be able to integrate new plant designs and components, to improve the results of modeling physical phenomena or quantify and thus reduce the uncertainties on these results. Currently, several H2020 Euratom projects are working on the improvement of these codes and methods. This article will focus on three of these projects: CAMIVVER (Codes And Methods Improvements for VVER comprehensive safety assessment), APAL (Advanced PTS Analysis for LTO), and sCO2-4-NPP (innovative SCO2-based heat removal technology for an increased level of safety of Nuclear Power Plants) in order to illustrate our thinking on the improvement of calculation frameworks. First, we will present the work and the approach adopted with regard to the different calculation codes and methods used in each of these three projects. We will then conclude with an overall analysis of these three approaches, highlighting the difficulties and successes of these three projects, and identifying areas of work for the general improvement of the calculation codes.

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Spoor, D., F. E. V. Leeuwen, N. Russell, et al. "Development and Internal Validation of an NTCP-model for Acute Coronary Events after Breast Cancer Radiotherapy: First Results of the MEDIRAD BRACE Study (H2020-Euratom-1.4 / 755523)." International Journal of Radiation Oncology*Biology*Physics 108, no. 3 (2020): S11—S12. http://dx.doi.org/10.1016/j.ijrobp.2020.07.2088.

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Caruggi, Federico, Antonio Cammi, Eric Cervi, Ronco Andrea Di, and Stefano Lorenzi. "Multiphysics modelling of gaseous fission products in the Molten Salt Fast Reactor." Nuclear Engineering and Design 392 (April 21, 2022): 111762. https://doi.org/10.1016/j.nucengdes.2022.111762.

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The Molten Salt Fast Reactor (MSFR) is a nuclear reactor concept under development in the framework of the H2020-Euratom project SAMOSAFER. Given its peculiar characteristics as a circulating-fuel reactor, new simulation tools need to be developed and tested for its study. In this work, a multiphysics solver previously developed in OpenFOAM is extended with new functionalities for the analysis of this reactor design. The main focus is the modelling of the behavior of Gaseous Fission Products (GFPs) inside the core and their interactions with a helium bubbling system, foreseen to remove both GFPs and metallic fission products through flotation. On the basis of an Euler-Euler solver able to model the presence of the two phases – namely the liquid fuel and the gaseous bubbles – , a multi-component mixture approach is adopted to simulate the behavior of GFP species in the core, with particular focus on their production, consumption, transport, mass exchange and removal to the off-gas system. The new capabilities are tested on both 2D and 3D MSFR cases, considering Xe-135 as reference nuclide, with focus on the efficiency of the bubbling system in the removal of GFPs from the salt. As main figure of merit of the removal capability, a cycle time related to the extraction of the specie from the system is defined and calculated for different conditions of helium injection. This work constitutes a further advancement in the development of the MSFR concept, extending the modelling capabilities of the previous multiphysics solver. Reliable estimation of the evolution of the gaseous fission products in the reactor core and the related effect of the helium bubbling system is a fundamental requirement for the analysis of the radioactive source term and for the prediction of the overall operating conditions of this innovative nuclear system.

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Frederix, E.M.A. "Estimates of noble metal particle growth in a molten salt reactor." Colloids and Surfaces A: Physicochemical and Engineering Aspects 655 (December 20, 2022): 130167. https://doi.org/10.1016/j.colsurfa.2022.130167.

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Within the H2020-Euratom project SAMOSAFER, research is currently ongoing into the Molten Salt Fast Reactor (MSFR) concept in which nuclear fuel is dissolved in a liquid salt. A major challenge in the MSFR is the online and offline treatment of salt in order to remove a plethora of fission products. Noble metals are a type of such fission products, the atoms of which are thought to coagulate into particles as a result of diffusion. Due to their low solubility, noble metal particles will deposit onto interfaces such as solid walls but also on bubbles, as was observed in the Molten Salt Reactor Experiment (MSRE) at Oak Ridge national laboratory. The relatively large interfacial area generated by bubbles makes online or offline bubbling, therefore, an interesting option to extract noble metals from the MSFR and to limit wall deposition. However, to understand the performance of the bubbling process, particle sizes must be known. Particle size distributions arise from a complex interplay of atomic formation by fission and decay, growth by coagulation and removal by interfacial deposition. In this paper, theory is developed to understand these mechanisms on a semi-analytical level, in order to provide estimates of noble metal particle growth in the MSFR. The governing partial differential equation is reduced to a set of ordinary differential equations using the method of moments, revealing the dynamics of the underlying physics. We show that large noble metal particles, up to the micrometer scale, can arise in the reactor, but only at very long operational times. Moreover, we show that the previously assumed ‘cycle time’ of noble metal particle removal of 30 s is only feasible at very high bubbling void fractions. The theory developed in this work contributes significantly to a qualitative understanding of the behavior of noble metals in an MSR. The theory can potentially help to explain certain phenomena observed in the MSRE and can assist in the future design of safe and reliable MSRs.

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Niederleithinger, Ernst, Vera Lay, Christian Köpp, Erika Holt, and Maria Oksa. "PREDIS: innovative ways for predisposal treatment and monitoring of low and medium radioactive waste." Safety of Nuclear Waste Disposal 1 (November 10, 2021): 9–10. http://dx.doi.org/10.5194/sand-1-9-2021.

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Abstract. The EURATOM PREDIS project (http://www.predis-h2020.eu, last access: 25 October 2021) targets the development and implementation of activities for predisposal treatment of radioactive waste streams other than nuclear fuel and high-level radioactive waste. It started on 1 September 2020 with a 4 year duration. The consortium includes 47 partners from 17 member states. The overall budget of the project is EUR 23.7 million, with EC contribution of EUR 14 million. The PREDIS project develops and increases the technological readiness level (TRL) of treatment and conditioning methodologies for wastes for which no adequate or industrially mature solutions are currently available, including metallic materials, liquid organic waste and solid organic waste. The PREDIS project also develops innovations in cemented waste handling and predisposal storage by testing and evaluating. The technical work packages align with priorities formulated within the Roadmap Theme 2 of EURAD (https://www.ejp-eurad.eu/sites/default/files/2021-09/2_Predisposal_Theme_Overview.pdf, last access: 15 October 2021), Nugenia Global Vision (https://snetp.eu/wp-content/uploads/2020/10/Global-vision-document-ves-1-april-2015-aa.pdf, last access: 15 October 2021) and with those identified by the project's industrial end users group (EUG). The PREDIS will produce tools guiding decision making on the added value of the developed technologies and their impact on the design, safety and economics of waste management and disposal. Four technical work packages are focusing on specific waste types: metallic, liquid organic, solid organic, and cemented wastes. For the first three, the main aim lies in processing, stabilizing, and packaging the different waste streams, e.g. by using novel geopolymers, to deliver items which are in line with national and international waste acceptance criteria. In contrast, the fourth technical work package has a different focus. To provide better ways for a safe and effective monitoring of cemented waste packages including prediction tools to assess the future integrity development during predisposal activities, several digital tools are evaluated and improved. Safety enhancement (e.g. less exposure of testing personnel) and cost-effectiveness are part of the intended impact. The work includes but is not limited to inspection methods, such as muon imaging, wireless sensors integrated into waste packages as well as external package and facility monitoring, such as remote fiber optic sensors. The sensors applied will go beyond radiation monitoring and include proxy parameters important for long-term integrity assessment (e.g. internal pressure). Sensors will also be made cost-effective to allow the installation of many more sensors compared to current practice. The measured data will be used in digital twins of the waste packages for specific simulations (geochemical, integrity) providing a prediction of future behavior. Machine learning techniques trained by the characterization of older waste packages will help to connect the models to the current data. All data (measured and simulated) will be collected in a joint database and connected to a decision framework to be used at actual facilities. The presentation includes detailed information about the various tools under consideration in the monitoring of cemented waste packages, their connection and first results of the research.

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Marinari, Ranieri, Paolo Favuzza, Davide Bernardi, Francesco Saverio Nitti, and Piazza Ivan Di. "CFD Optimization of the Resistivity Meter for the IFMIF-DONES Facility." April 29, 2021. https://doi.org/10.3390/en14092543.

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A detailed study of lithium-related topics in the IFMIF-DONES facility is currently being promoted and supported within the EUROfusion action, paying attention to different pivotal aspects including lithium flow stability and the monitoring and extraction of impurities. The resistivity meter is a device able to monitor online non-metallic impurities (mainly nitrogen) in flowing lithium. It relies on the variation of the electric resistivity produced by dissolved anions: the higher the concentration of impurities in lithium, the higher the resistivity measured. The current configuration of the resistivity meter has shown different measuring issues during its operation. All these issues reduce the accuracy of the measurements performed with this instrument and introduce relevant noise affecting the resistance value. This paper proposes different upgrades, supported by CFD simulations, to optimize lithium flow conditions and to reduce measurement problems. Owing to these upgrades, a new design of the resistivity meter has been achieved, which is simpler and easier to manufacture.

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Murari, Andrea, Emmanuele Peluso, Michele Lungaroni, Riccardo Rossi, Michela Gelfusa, and NA NA. "Investigating the Physics of Tokamak Global Stability with Interpretable Machine Learning Tools." September 24, 2020. https://doi.org/10.3390/app10196683.

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The inadequacies of basic physics models for disruption prediction have induced the community to increasingly rely on data mining tools. In the last decade, it has been shown how machine learning predictors can achieve a much better performance than those obtained with manually identified thresholds or empirical descriptions of the plasma stability limits. The main criticisms of these techniques focus therefore on two different but interrelated issues: poor "physics fidelity" and limited interpretability. Insufficient "physics fidelity" refers to the fact that the mathematical models of most data mining tools do not reflect the physics of the underlying phenomena. Moreover, they implement a black box approach to learning, which results in very poor interpretability of their outputs. To overcome or at least mitigate these limitations, a general methodology has been devised and tested, with the objective of combining the predictive capability of machine learning tools with the expression of the operational boundary in terms of traditional equations more suited to understanding the underlying physics. The proposed approach relies on the application of machine learning classifiers (such as Support Vector Machines or Classification Trees) and Symbolic Regression via Genetic Programming directly to experimental databases. The results are very encouraging. The obtained equations of the boundary between the safe and disruptive regions of the operational space present almost the same performance as the machine learning classifiers, based on completely independent learning techniques. Moreover, these models possess significantly better predictive power than traditional representations, such as the Hugill or the beta limit. More importantly, they are realistic and intuitive mathematical formulas, which are well suited to supporting theoretical understanding and to benchmarking empirical models. They can also be deployed easily and efficiently in real-time feedback systems.

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Marigrazia, Moscardini, Galleni Francesco, Pucciarelli Andrea, Martelli Daniele, and Forgione Nicola. "Numerical Analysis of the CIRCE-HERO PLOFA Scenarios." October 21, 2020. https://doi.org/10.3390/app10207358.

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The present work deals with simulations carried out at the University of Pisa by using the System Thermal Hydraulics code RELAP5/Mod3.3 to support the experimental campaign conducted at the ENEA (Energia Nucleare ed Energie Alternative) Brasimone Research Centre on the CIRColazione Eutettico—Heavy liquid mEtal pRessurized water cOoled tubes (CIRCE-HERO) facility. CIRCE is an integral effect pool type facility dedicated to the study of innovative nuclear systems and cooled by heavy liquid metal, while HERO is a heat exchanger heavy liquid metal/ pressurized cooling water system hosted inside the CIRCE facility. Beside the H2020 project Multi-Purpose Hybrid Research Reactor for High-Tech Applications (MYRRHA) Research and Transmutation Endeavour (MYRTE), a series of experiments were performed with the CIRCE-HERO facility, for both nominal steady-state settings and accidental scenarios. In this framework, the RELAP5/Mod3.3 code was used to simulate the experimental tests assessing the heat losses of the facility and analyzing the thermal hydraulics phenomena occurring during the postulated Protected Loss Of Flow Accident (PLOFA). The modified version Mod. 3.3 of the source code RELAP5 was developed by the University of Pisa to include the updated thermo–physical properties and convective heat transfer correlations suitable for heavy liquid metals. After reproducing the facility through an accurate nodalization, boundary conditions were applied according to the experiments. Then, the PLOFA scenarios were reproduced by implementing the information obtained by the experimental campaign. Sensitivity analyses of the main parameters affecting the thermofluidynamics of the Lead-Bismuth Eutectic (LBE) were carried out. In the simulated scenario, the LBE mass flow rate strongly depends on the injected argon flow time trend. The numerical results are in agreement with the experimental data, however further investigations are planned to analyze the complex phenomena involved.

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Mistrangelo, Chiara, Leo Bühler, Ciro Alberghi, et al. "MHD R&D Activities for Liquid Metal Blankets." October 14, 2021. https://doi.org/10.3390/en14206640.

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According to the most recently revised European design strategy for DEMO breeding blankets, mature concepts have been identified that require a reduced technological extrapolation towards DEMO and will be tested in ITER. In order to optimize and finalize the design of test blanket modules, a number of issues have to be better understood that are related to the magnetohydrodynamic (MHD) interactions of the liquid breeder with the strong magnetic field that confines the fusion plasma. The aim of the present paper is to describe the state of the art of the study of MHD effects coupled with other physical phenomena, such as tritium transport, corrosion and heat transfer. Both numerical and experimental approaches are discussed, as well as future requirements to achieve a reliable prediction of these processes in liquid metal blankets.

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Chmielewski, P., R. Zagórski, G. Telesca, et al. "TECXY simulations of Ne seeding in JET high power scenarios." March 27, 2021. https://doi.org/10.1016/j.nme.2021.100962.

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Forte, Ruggero, Pierluigi Chiovaro, Maio Pietro Alessandro Di, and Nasr Ghoniem. "Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets." August 25, 2021. https://doi.org/10.1016/j.nme.2021.101058.

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Bernardi, Mario Luca, Marta Cimitile, Fabio Martinelli, and Francesco Mercaldo. "Driver and Path Detection through Time-Series Classification." March 22, 2018. https://doi.org/10.1155/2018/1758731.

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Driver identification and path kind identification are becoming very critical topics given the increasing interest of automobile industry to improve driver experience and safety and given the necessity to reduce the global environmental problems. Since in the last years a high number of always more sophisticated and accurate car sensors and monitoring systems are produced, several proposed approaches are based on the analysis of a huge amount of real-time data describing driving experience. In this work, a set of behavioral features extracted by a car monitoring system is proposed to realize driver identification and path kind identification and to evaluate driver's familiarity with a given vehicle. The proposed feature model is exploited using a time-series classification approach based on a multilayer perceptron (MLP) network to evaluate their effectiveness for the goals listed above. The experiment is done on a real dataset composed of totally 292 observations (each observation consists of a given person driving a given car on a predefined path) and shows that the proposed features have a very good driver and path identification and profiling ability.

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Kirschner, A., D. Matveev, D. Borodin, et al. "Modelling of the material transport and layer formation in the divertor of JET: Comparison of ITER-like wall with full carbon wall conditions." November 1, 2014. https://doi.org/10.1016/j.jnucmat.2014.10.072.

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Mishchenko, Alexey, Alberto Bottino, Roman Hatzky, Eric Sonnendrücker, Ralf Kleiber, and Axel Könies. "Mitigation of the cancellation problem in the gyrokinetic particle-in-cell simulations of global electromagnetic modes." August 21, 2017. https://doi.org/10.1063/1.4997540.

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Electromagnetic gyrokinetic particle-in-cell simulations have been inhibited for long time by numerical problems. This paper discusses the origin of these problems. It also gives an overview and summary of the mitigation techniques.

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Kurutz, U., R. Friedl, and U. Fantz. "Investigations on Cs-free alternatives for negative ion formation in a low pressure hydrogen discharge at ion source relevant parameters." May 4, 2017. https://doi.org/10.1088/1361-6587/aa7120.

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Huang, Zhouji, Stefano Coda, and NA NA. "Dependence of density fluctuations on shape and collisionality in positive- and negative-triangularity tokamak plasmas." August 20, 2018. https://doi.org/10.1088/1361-6587/aadb59.

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Bauer, J., T. Schwarz-Selinger, K. Schmid, M. Balden, A. Manhard, and Toussaint U. von. "Influence of near-surface blisters on deuterium transport in tungsten." May 10, 2017. https://doi.org/10.1088/1741-4326/aa7212.

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Widdowson, A., J.P. Coad, E. Alves, et al. "Overview of fuel inventory in JET with the ITER-like wall." May 22, 2017. https://doi.org/10.1088/1741-4326/aa7475.

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Koechl, F., A. Loarte, V. Parail, et al. "Modelling of transitions between L- and H-mode in JET high plasma current plasmas and application to ITER scenarios including tungsten behaviour." May 26, 2017. https://doi.org/10.1088/1741-4326/aa7539.

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Igochine, V., P. Piovesan, I.G.J. Classen, et al. "MHD limits and plasma response in high-beta hybrid operations in ASDEX Upgrade." June 27, 2017. https://doi.org/10.1088/1741-4326/aa7bf9.

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Mao, R., N. Fedorczak, G. Ciraolo, et al. "Impact of an alternative divertor configuration on plasma detachment: pure deuterium simulations using the SOLEDGE2D-EIRENE edge transport code for HL-2M scenarios." July 8, 2019. https://doi.org/10.1088/1741-4326/ab3005.

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Ajmalghan, M., Z.A. Piazza, E.A. Hodille, and Y. Ferro. "Surface coverage dependent mechanisms for the absorption and desorption of hydrogen from the W(1 1 0) and W(1 0 0) surfaces: a density functional theory investigation." July 19, 2019. https://doi.org/10.1088/1741-4326/ab33e7.

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Crozet, Marielle, Séverine Demeyer, Valérie Lourenço, Margarita Herranz, and Sven Boden. "Analysis of the comparison of in situ measurements made on biological shielding of the BR3 nuclear reactor." Journal of Radioanalytical and Nuclear Chemistry, May 5, 2022. http://dx.doi.org/10.1007/s10967-022-08319-9.

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AbstractINSIDER (Improved Nuclear SIte characterization for waste minimization in D&D operations under constrained EnviRonment) was a European project funded under the H2020-EURATOM programme and launched in June 2017. The project was coordinated by the French Commissariat à l’énergie atomique et aux énergies alternatives (CEA), it had a total duration of 4 years and covered a budget of 4 M€. INSIDER’s work was performed by 5 technical working groups (WG) which brought together 18 institutions from 10 countries, leading to a total of 68 participating researchers. The objective of the project was to optimise the radiological characterisation of nuclear installations in constrained environments in order to obtain an accurate estimate of the content of contaminated materials as well as to optimise the quantity of contaminated materials to be treated as waste. The focus of this paper is on the statistical analysis of an interteam comparison of measurement results (dose rate, total gamma measurement, and gamma spectrometry) made in situ at the BR3 reactor, Belgium.

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Nikiforovа, Liliia, Anzhelika Azarova, Anatoliy Shiyan та Olena Zhytkevych. "Use of international grant programs Horizon 2020 та Horizon Europe in the digital economy". Innovation and Sustainability, 30 вересня 2022, 176–85. http://dx.doi.org/10.31649/ins.2022.3.176.185.

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The work reveals the status and prospects of using international grant programs of Horizon 2020 and Horizon Europe in the digital economy cluster. It is shown that despite the existence of a large number of international grant projects, in particular within the framework programs of Horizon 2020 and Horizon Europe, the problem of increasing the number of participants from among Ukrainian scientists and scientific teams in these projects remains open. It is shown that there is a gap between the Ukrainian scientific and technical community and the world in the field of obtaining funding for grant projects. The analysis of the features of the use of international framework programs of Horizon 2020 and Horizon Europe in the digital economy cluster was carried out. In particular, a detailed analysis of the supported grant projects in the Horizon 2020 program was carried out with the participation of Ukrainian scientific teams and the role of Ukraine as a project coordinator. The specifics of the topic and the choice of the cluster of funded grant projects were studied. In particular, in the field of digitalization, the research was conducted in the context of such clusters as H2020-EU.2/H2020-EU.2.1 and H2020-EU.2.3.1, which accounted for 12.8% of all funded grant projects within the eighth framework program of Horizon 2020. As for the Horizon Europe program, the research was conducted under all grant projects in which Ukraine participated, including the Euratom program. The budget of the cluster programs in the field of digitalization, which are most in demand by Ukrainian scientists, was also analyzed, the priority areas of providing grants in the ninth framework program of Horizon Europe were determined, and the main key factors of supporting grant projects in the framework program of Horizon 2020 were identified. It is shown that the European Commission, when choosing competitive projects, gives Ukrainian teams more chances to receive funding for a grant project if it is related to the goals of the European Union.

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Karine, Liger, Grisolia Christian, Cristescu Ion, et al. "Overview of the TRANSAT (TRANSversal Actions for Tritium) project." May 27, 2018. https://doi.org/10.1016/j.fusengdes.2018.01.037.

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Abstract:

In the framework of H2020 Euratom research and innovation programme, TRANSAT (TRANSversal Actions for Tritium) is a 4 years multidisciplinary project built to contribute to Research and Innovation on cross-cutting activities required to improve knowledge on tritium management in fission and fusion facilities. TRANSAT was built to answer the main following challenges: tritium release mitigation strategies, waste management improvement and refinement of the knowledge in the field of radiotoxicity, radiobiology and dosimetry. To evaluate the scientific tasks that can be covered by TRANSAT, at each step of the tritium life cycle, all the open issues that are not yet tackled by European research activities or former studies have been determined. This general landscape has been constrained to crosscutting activities on fusion and fission. The aim of this paper is to give a general overview of the project structure and its main goals, including a detailed description of the technical topics that will be covered by the eighteen partners of the project. In particular, TRANSAT project will cover actions from tritium permeation barrier development, innovative online effluent treatments, tritium migration assessment modelling tools to tritiated waste characterization and confinement studies. In addition, part of the project will focus on radiotoxicity, radioecology, radiobiology and dosimetry on tritiated particles produced during dismantling, whose impacts have never been addressed. In order to promote TRANSAT results, a dedicated workpackage is planned to disseminate the project outcomes by means of communication actions, summer schools and development of new collaboration with external parties.

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