Relevant bibliographies by topics / H2020 Euratom

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Academic literature on the topic 'H2020 Euratom'

Author: Grafiati
Published: 7 June 2025
Last updated: 2 August 2025

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Journal articles on the topic "H2020 Euratom"

1

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 uncertai
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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 analyzin
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3

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 methodolog
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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
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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 quantifica
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6

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 consi
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7

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 t
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8

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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9

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 bo
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10

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
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Conference papers on the topic "H2020 Euratom"

1

Varju, Tamás, Attila Kiss, Csenge Antók, et al. "Current Results of BME NTI in the ECC-SMART Project: Different Analysis on the SCW-SMR." In 2024 31st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2024. http://dx.doi.org/10.1115/icone31-135760.

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Abstract BME, as a consortium member, is participating in the ECC-SMART project, which has been awarded an EU/EURATOM/H2020 grant in 2020, and is researching the development of a supercritical water-cooled small modular reactor concept called SCW-SMR. This paper summarizes the research work carried out so far at BME within the framework of the project. Firstly, several international benchmarks were modelled by the APROS system code and the Ansys CFX CFD software package in order to demonstrate their applicability for the thermal hydraulics analysis of SCW. Later, a complete reactor vessel and
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