Free Access to the whole issue

EPJ Nuclear Sciences & Technologies

Volume 5 (2019)

Export the citation of the selected articles Export
Select all

Euratom Research and Training in 2019: the Awards collection

R. Garbil, C. Davies and D. Diaconu (Guest editors)

Open Access

New composite material based on heavy concrete reinforced by basalt-boron fiber for radioactive waste management 22

Iryna Romanenko, Maryna Holiuk, Pavlo Kutsyn, Iryna Kutsyna, Hennadii Odynokin, Anatolii Nosovskyi, Vitalii Pastsuk, Madis Kiisk, Alex Biland et al. (2 more)

Published online: 10 December 2019

DOI: https://doi.org/10.1051/epjn/2019050

Open Access

Innovative technologies in training and education for maintenance team of NPPs 21

Róbert Soós, Bence Balogh, Gergely Dobos, Szabolcs Szávai and Judit Dudra

Published online: 06 December 2019

DOI: https://doi.org/10.1051/epjn/2019053

Open Access

3D convolutional and recurrent neural networks for reactor perturbation unfolding and anomaly detection 20

Aiden Durrant, Georgios Leontidis and Stefanos Kollias

Published online: 29 November 2019

DOI: https://doi.org/10.1051/epjn/2019047

Open Access

Stability studies of GANEX system under different irradiation conditions 19

Iván Sánchez-García, Hitos Galán, Jose Manuel Perlado and Joaquín Cobos

Published online: 29 November 2019

DOI: https://doi.org/10.1051/epjn/2019049

Progress in the Science and Technology of Nuclear Reactors using Molten Salts

Jan Leen Kloosterman, Elsa Merle and Jean Ragusa (Guest editors)

Safety Evaluation

Open Access

Application of the lines of defence method to the molten salt fast reactor in the framework of the SAMOFAR project 18

Stéphane Beils, Delphine Gérardin, Anna Chiara Uggenti, Andrea Carpignano, Sandra Dulla, Elsa Merle, Daniel Heuer and Michel Allibert

Published online: 11 November 2019

DOI: https://doi.org/10.1051/epjn/2019031

Physics

Open Access

Application of multiphysics model order reduction to doppler/neutronic feedback 17

Peter German, Jean C. Ragusa and Carlo Fiorina

Published online: 14 November 2019

DOI: https://doi.org/10.1051/epjn/2019034

Open Access

Influence of molten salt-(FLiNaK) thermophysical properties on a heated tube using CFD RANS turbulence modeling of an experimental testbed 16

Ramiro Freile and Mark Kimber

Published online: 14 November 2019

DOI: https://doi.org/10.1051/epjn/2019027

Fuel cycle evaluation

Open Access

Breed-and-burn fuel cycle in molten salt reactors 15

Boris Hombourger, Jiři Křepel and Andreas Pautz

Published online: 15 November 2019

DOI: https://doi.org/10.1051/epjn/2019026

Design of reactor

Open Access

Simplified 0-D semi-analytical model for fuel draining in molten salt reactors 14

Francesco Di Lecce, Antonio Cammi, Sandra Dulla, Stefano Lorenzi and Piero Ravetto

Published online: 15 November 2019

DOI: https://doi.org/10.1051/epjn/2019028

Open Access

Development of a control-oriented power plant simulator for the molten salt fast reactor 13

Claudio Tripodo, Andrea Di Ronco, Stefano Lorenzi and Antonio Cammi

Published online: 11 November 2019

DOI: https://doi.org/10.1051/epjn/2019029

Design of components

Open Access

Heat exchanger design studies for molten salt fast reactor 12

Uğur Köse, Ufuk Koç, Latife Berrin Erbay, Erdem Öğüt and Hüseyin Ayhan

Published online: 11 November 2019

DOI: https://doi.org/10.1051/epjn/2019032

Open Access

Development of a cold plug valve with fluoride salt 9

Julien Giraud, Veronique Ghetta, Pablo Rubiolo and Mauricio Tano Retamales

Published online: 26 August 2019

DOI: https://doi.org/10.1051/epjn/2019005

Open Access

Feedback from experimental isotopic compositions of used nuclear fuels on neutron cross sections and cumulative fission yields of the JEFF-3.1.1 library by using integral data assimilation 24

Axel Rizzo, Claire Vaglio-Gaudard, Gilles Noguere, Romain Eschbach, Gabriele Grassi and Julie-Fiona Martin

Published online: 23 December 2019

DOI: https://doi.org/10.1051/epjn/2019056

Open Access

Microstructure and mechanical properties relationship of additively manufactured 316L stainless steel by selective laser melting 23

Anne-Helene Puichaud, Camille Flament, Aziz Chniouel, Fernando Lomello, Elodie Rouesne, Pierre-François Giroux, Hicham Maskrot, Frederic Schuster and Jean-Luc Béchade

Published online: 19 December 2019

DOI: https://doi.org/10.1051/epjn/2019051

Open Access

Modelling of fine fragmentation and fission gas release of UO₂ fuel in accident conditions 11

Lars O. Jernkvist

Published online: 08 November 2019

DOI: https://doi.org/10.1051/epjn/2019030

Open Access

Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour 10

Fabien Rouillard, Brigitte Duprey, Jean-Louis Courouau, Raphaël Robin, Pascal Aubry, Cécile Blanc, Michel Tabarant, Hicham Maskrot, Laetitia Nicolas, Martine Blat-Yrieix et al. (2 more)

Published online: 05 November 2019

DOI: https://doi.org/10.1051/epjn/2019025

Open Access

How to obtain an enhanced extended uncertainty associated with decay heat calculations of industrial PWRs using the DARWIN2.3 package 8

Jordan Huyghe, Vanessa Vallet, David Lecarpentier, Christelle Reynard-Carette and Claire Vaglio-Gaudard

Published online: 29 July 2019

DOI: https://doi.org/10.1051/epjn/2019002

Highlight

Open Access

Quick calculation of damage for ion irradiation: implementation in Iradina and comparisons to SRIM 7

Jean-Paul Crocombette and Christian Van Wambeke

Published online: 15 May 2019

DOI: https://doi.org/10.1051/epjn/2019003

Open Access

Karlsruhe Nuclide Chart – New 10th edition 2018 6

Zsolt Sóti, Joseph Magill and Raymond Dreher

Published online: 13 May 2019

DOI: https://doi.org/10.1051/epjn/2019004

Open Access

Stimulating niche nurturing process for heat production with nuclear plants in France: A multi-level perspective 5

Martin Leurent

Published online: 28 February 2019

DOI: https://doi.org/10.1051/epjn/2019001

Open Access

The Uranie platform: an open-source software for optimisation, meta-modelling and uncertainty analysis 4

Jean-Baptiste Blanchard, Guillaume Damblin, Jean-Marc Martinez, Gilles Arnaud and Fabrice Gaudier

Published online: 28 February 2019

DOI: https://doi.org/10.1051/epjn/2018050

Open Access

Pin to pin neutron flux reconstruction in a PWR reactor using support vector regression (SVR) technique 3

W.F.P. Neto, A.C.M. Alvim, F.C. Silva and L.G.M. Alvim

Published online: 19 February 2019

DOI: https://doi.org/10.1051/epjn/2018051

Open Access

Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects 2

Mariya Brovchenko, Jan-Leen Kloosterman, Lelio Luzzi, Elsa Merle, Daniel Heuer, Axel Laureau, Olga Feynberg, Victor Ignatiev, Manuele Aufiero, Antonio Cammi et al. (7 more)

Published online: 19 February 2019

DOI: https://doi.org/10.1051/epjn/2018052

Open Access

CADOR “Core with Adding DOppleR effect” concept application to sodium fast reactors 1

Alain Zaetta, Bruno Fontaine, Pierre Sciora, Romain Lavastre, Robert Jacqmin, Vincent Pascal, Michel Pelletier, Gérard Mignot and Aurélien Jankowiak

Published online: 12 February 2019

DOI: https://doi.org/10.1051/epjn/2018049

EPJ Nuclear Sciences & Technologies

Volume 5 (2019)

Euratom Research and Training in 2019: the Awards collection

New composite material based on heavy concrete reinforced by basalt-boron fiber for radioactive waste management 22

Innovative technologies in training and education for maintenance team of NPPs 21

3D convolutional and recurrent neural networks for reactor perturbation unfolding and anomaly detection 20

Stability studies of GANEX system under different irradiation conditions 19

Progress in the Science and Technology of Nuclear Reactors using Molten Salts

Safety Evaluation

Application of the lines of defence method to the molten salt fast reactor in the framework of the SAMOFAR project 18

Physics

Application of multiphysics model order reduction to doppler/neutronic feedback 17

Influence of molten salt-(FLiNaK) thermophysical properties on a heated tube using CFD RANS turbulence modeling of an experimental testbed 16

Fuel cycle evaluation

Breed-and-burn fuel cycle in molten salt reactors 15

Design of reactor

Simplified 0-D semi-analytical model for fuel draining in molten salt reactors 14

Development of a control-oriented power plant simulator for the molten salt fast reactor 13

Design of components

Heat exchanger design studies for molten salt fast reactor 12

Development of a cold plug valve with fluoride salt 9

Feedback from experimental isotopic compositions of used nuclear fuels on neutron cross sections and cumulative fission yields of the JEFF-3.1.1 library by using integral data assimilation 24

Microstructure and mechanical properties relationship of additively manufactured 316L stainless steel by selective laser melting 23

Modelling of fine fragmentation and fission gas release of UO2 fuel in accident conditions 11

Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour 10

How to obtain an enhanced extended uncertainty associated with decay heat calculations of industrial PWRs using the DARWIN2.3 package 8

Quick calculation of damage for ion irradiation: implementation in Iradina and comparisons to SRIM 7

Karlsruhe Nuclide Chart – New 10th edition 2018 6

Stimulating niche nurturing process for heat production with nuclear plants in France: A multi-level perspective 5

The Uranie platform: an open-source software for optimisation, meta-modelling and uncertainty analysis 4

Pin to pin neutron flux reconstruction in a PWR reactor using support vector regression (SVR) technique 3

Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects 2

CADOR “Core with Adding DOppleR effect” concept application to sodium fast reactors 1

Modelling of fine fragmentation and fission gas release of UO₂ fuel in accident conditions 11