Found: 54
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INSIDER UC2: the BR3 biological shield preliminary results and future work.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019054
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- Article
UC1 sampling plan, liquid waste storage tanks, JRC Ispra.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019043
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INSIDER WP5 (in situ measurements): developed activities, main results and conclusions.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019061
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Metrology applications to D&D issues: issues at stake for INSIDER European project.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019052
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Development of a user-friendly guideline for data analysis and sampling design strategy.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020006
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- Article
Use case 3: post accidental site remediation − CEA.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019060
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- Article
Analysis of radionuclides in microsystem: application to the selective recovery of <sup>55</sup>Fe by solvent extraction.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020002
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- Article
INSIDER.
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- 2020
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- Publication type:
- Editorial
COSICAF, a fission chamber simulation tool for academic purposes.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020011
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Safety assurance through advances in long-term operation.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019015
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Reactor performance, system reliability, instrumentation and control.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019017
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Advanced numerical simulation and modelling for reactor safety − contributions from the CORTEX, HPMC, McSAFE and NURESAFE projects.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019006
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Safety assessments and severe accidents, impact of external events on nuclear power plants and on mitigation strategies.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019010
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Innovative Gen-II/III and research reactors' fuels and materials.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019008
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- Article
Innovative and safe supply of fuels for reactors.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019013
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Probabilistic safety assessment for internal and external events/European projects H2020-NARSIS and FP7-ASAMPSA_E.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019012
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Euratom success stories in facilitating pan-European education and training collaborative efforts.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019016
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Nuclear cogeneration with high temperature reactors.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019023
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Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV fast neutron systems.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019007
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- Article
Partitioning and transmutation strategy R&D for nuclear spent fuel: the SACSESS and GENIORS projects.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019009
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- Article
Fuel fabrication and reprocessing issues: the ASGARD project.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019014
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- Article
Nuclear and radiological emergency management and preparedness.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019011
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- Article
Infrastructure and international cooperation in research and knowledge transfer: supporting access to key infrastructures and pan-European research − lessons learned.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019019
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Nuclear data research supported by EURATOM: CHANDA, ERINDA and EUFRAT.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019024
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Education, training and mobility: towards a common effort to assure a future workforce in Europe and abroad.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019018
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Supporting infrastructures and research reactors: status, needs and international cooperation, IAEA ICERR (International CEntres based on Research Reactors) and IGORR (International Group on Research Reactors), FP7 and H2020 JHR access rights.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019022
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- Article
Advances on GenIV structural and fuel materials and cross-cutting activities between fission and fusion.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019021
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Improved expertise in radiation protection, nuclear chemistry and geological disposal.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019020
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Euratom Research and Training in 2019: challenges, achievements and future perspectives.
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- 2020
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- Publication type:
- Editorial
EURAD − the European Joint Programme for research on radioactive waste management between EU members states national programmes.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019044
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Science underpinning the safety case of deep geological repositories − challenges in the past and in the future and how to maintain knowledge and competence during operation.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019037
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Thermal treatment for radioactive waste minimisation.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019040
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Beacon: bentonite mechanical evolution.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019045
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Needs of countries with longer timescale for deep geological repository implementation.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019042
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Partitioning and transmutation contribution of MYRRHA to an EU strategy for HLW management and main achievements of MYRRHA related FP7 and H2020 projects: MYRTE, MARISA, MAXSIMA, SEARCH, MAX, FREYA, ARCAS.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019038
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A nuclear owner/operator perspective on ways and means for joint programming on predisposal activities.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019039
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- Article
JRC in Euratom Research and Training Programme − 2014–2020.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019036
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SESAME project: advancements in liquid metal thermal hydraulics experiments and simulations.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019046
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Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO<sub>2</sub> on Cs, Mo and Ba speciation.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019058
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Effects of the initial granular structure of clay sealing materials on their swelling properties: experiments and DEM simulations.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019059
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- Article
Influence of the dissolved hydrogen concentration on the radioactive contamination of the primary loops of DOEL-4 PWR using the OSCAR code.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020005
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- Article
Preliminary proliferation study of the molten salt fast reactor.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019062
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- Article
Effect of the [U(IV)]/[U(III)] ratio on selective chromium corrosion and tellurium intergranular cracking of Hastelloy N alloy in the fuel LiF-BeF<sub>2</sub>-UF<sub>4</sub> salt.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019033
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Editorial : progress in the science and technology of nuclear reactors using molten salts.
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- 2020
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- Publication type:
- Editorial
Uncertainty propagation based on correlated sampling technique for nuclear data applications.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020003
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- Article
Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020004
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- Article
Validating nuclear data uncertainties obtained from a statistical analysis of experimental data with the "Physical Uncertainty Bounds" method.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020007
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- Article
Numerical design of thorium and uranium fuel samples irradiation in lead environment.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020014
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- Article
Generation of correlation and covariance matrices for the recommended temporal DN parameters in 6- and 8-group models.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020013
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- Article
The knowledge management on the design of a generation IV sodium fast reactor project at CEA. The case and methodology applied on the Astrid project.
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- EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020016
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- Article