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EPJ Nuclear Sciences & Technologies

Volume 7 (2021)

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A tribute to Massimo Salvatores' scientific work

Open Access

Editorial

A journey into Massimo Salvatores scientific work E1

Alain Zaetta, Cyrille De Saint Jean and Robert Jacqmin

Published online: 24 May 2021

DOI: 10.1051/epjn/2021009

Open Access

Regular Article

Two examples of recent advances in sensitivity calculations 13

Elias Vandermeersch, Maxence Maillot, Pierre Tamagno, Jean Tommasi and Cyrille De Saint Jean

Published online: 16 August 2021

DOI: 10.1051/epjn/2021012

Open Access

Regular Article

Massimo Salvatores: integral experiments and their use for the validation of nuclear data and the neutronic design of advanced nuclear systems 11

Giuseppe Palmiotti, Patrick Blaise and Frédéric Mellier

Published online: 30 June 2021

DOI: 10.1051/epjn/2021007

Open Access

Regular Article

Nuclear data assimilation, scientific basis and current status 9

Evgeny Ivanov, Cyrille De Saint-Jean and Vladimir Sobes

Published online: 06 May 2021

DOI: 10.1051/epjn/2021008

Open Access

Regular Article

The heuristically-based generalized perturbation theory 7

Augusto Gandini

Published online: 18 March 2021

DOI: 10.1051/epjn/2021003

Fuel Cycle Simulation TWoFCS 2021

Open Access

Regular Article

Application of sensitivity analysis in DYMOND/Dakota to fuel cycle transition scenarios 26

S. Richards and B. Feng

Published online: 21 December 2021

DOI: 10.1051/epjn/2021024

Open Access

Regular Article

Development of a MOX equivalence Python code package for ANICCA 25

Bart Vermeeren and Hubert Druenne

Published online: 21 December 2021

DOI: 10.1051/epjn/2021023

Open Access

Regular Article

Pu multi-recycling scenarios towards a PWR fleet for a stabilization of spent fuel inventories in France 23

Fanny Courtin, Camille Laguerre, Philippe Miranda, Christine Chabert and Guillaume Martin

Published online: 09 December 2021

DOI: 10.1051/epjn/2021022

Open Access

Regular Article

Enrichment dynamics for advanced reactor HALEU support 22

Amanda M. Bachmann, Roberto Fairhurst-Agosta, Zoë Richter, Nathan Ryan and Madicken Munk

Published online: 01 December 2021

DOI: 10.1051/epjn/2021021

Open Access

Regular Article

Estimation of the vitrified canister production for a PWR fleet with the CLASS code 21

Léa Tillard, Xavier Doligez, Gérald Senentz, Marc Ernoult, Jiali Liang and Nicolas Thiollière

Published online: 25 November 2021

DOI: 10.1051/epjn/2021020

Open Access

Regular Article

Impact of disruption between options of plutonium multi-recycling in PWRs and in SFRs 20

Jiali Liang, Marc Ernoult, Xavier Doligez, Sylvain David and Nicolas Thiollière

Published online: 15 November 2021

DOI: 10.1051/epjn/2021018

Open Access

Regular Article

NMB4.0: development of integrated nuclear fuel cycle simulator from the front to back-end 19

Tomohiro Okamura, Ryota Katano, Akito Oizumi, Kenji Nishihara, Masahiko Nakase, Hidekazu Asano and Kenji Takeshita

Published online: 03 November 2021

DOI: 10.1051/epjn/2021019

Open Access

Regular Article

Impact of H in H₂O thermal scattering data on depletion calculation: k_∞, nuclide inventory and decay heat 24

Dimitri Rochman, Mathieu Hursin, Alexander Vasiliev and Hakim Ferroukhi

Published online: 21 December 2021

DOI: 10.1051/epjn/2021027

Open Access

Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat 18

Dimitri Rochman, Alexander Vasiliev, Hakim Ferroukhi and Mathieu Hursin

Published online: 28 October 2021

DOI: 10.1051/epjn/2021017

Open Access

Regular Article

A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors 17

Amine Hajji, Christine Coquelet-Pascal and Patrick Blaise

Published online: 22 October 2021

DOI: 10.1051/epjn/2021016

Open Access

Regular Article

Delayed gamma fraction determination in the zero power reactor CROCUS 16

Oskari Pakari, Tom Mager, Vincent Lamirand, Pavel Frajtag and Andreas Pautz

Published online: 23 September 2021

DOI: 10.1051/epjn/2021015

Open Access

Regular Article

France–Japan synthesis concept on sodium-cooled fast reactor review of a joint collaborative work 15

Gilles Rodriguez, Frédéric Varaine, Laurent Costes, Christophe Venard, Frédéric Serre, Frédéric Chanteclair, Marie-Sophie Chenaud, Franck. Dechelette, Edouard Hourcade, David Plancq et al. (24 more)

Published online: 03 September 2021

DOI: 10.1051/epjn/2021014

Open Access

Regular Article

Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat 14

Dimitri Rochman, Alexander Vasiliev, Hakim Ferroukhi, Mathieu Hursin, Raphaelle Ichou, Julien Taforeau and Teodosi Simeonov

Published online: 24 August 2021

DOI: 10.1051/epjn/2021013

Open Access

Regular Article

Muon radiography to visualise individual fuel rods in sealed casks 12

Thomas Braunroth, Nadine Berner, Florian Rowold, Marc Péridis and Maik Stuke

Published online: 15 June 2021

DOI: 10.1051/epjn/2021010

Open Access

Regular Article

CONRAD – a code for nuclear data modeling and evaluation 10

Cyrille De Saint Jean, Pierre Tamagno, Pascal Archier and Gilles Noguere

Published online: 11 June 2021

DOI: 10.1051/epjn/2021011

Open Access

Regular Article

A multivariate representation of compressed pin-by-pin cross sections 8

Daniele Tomatis

Published online: 07 April 2021

DOI: 10.1051/epjn/2021006

Open Access

Regular Article

Sea container inspection with tagged neutrons 6

Bertrand Pérot, Cédric Carasco, Cyrille Eléon, Sébastien Bernard, Alix Sardet, Wassila El Kanawati, Clément Deyglun, Grégory Perret, Guillaume Sannié, Vladivoj Valkovic et al. (12 more)

Published online: 17 March 2021

DOI: 10.1051/epjn/2021004

Open Access

Regular Article

Fission yields and cross sections: correlated or not? 5

Dimitri Alexandre Rochman and Eric Bauge

Published online: 17 March 2021

DOI: 10.1051/epjn/2021005

Open Access

Regular Article

Prediction of crack propagation kinetics through multipoint stochastic simulations of microscopic fields 4

Etienne Le Mire, Emilien Burger, Bertrand Iooss and Chu Mai

Published online: 19 February 2021

DOI: 10.1051/epjn/2021001

Open Access

Regular Article

VVUQ of a thermal-hydraulic multi-scale tool on unprotected loss of flow accident in SFR reactor 3

Nathalie Marie, Simon Li, Amandine Marrel, Michel Marquès, Sophie Bajard, Annick Tosello, Jorge Perez, Baptiste Grosjean, Antoine Gerschenfeld, Marine Anderhuber et al. (4 more)

Published online: 05 February 2021

DOI: 10.1051/epjn/2021002

Open Access

Regular Article

A new direction in PWR simplification 2

Nicolaas M. Bonhomme

Published online: 21 January 2021

DOI: 10.1051/epjn/2020020

Open Access

Regular Article

A simplified analysis of the Chernobyl accident 1

Bertrand Mercier, Di Yang, Ziyue Zhuang and Jiajie Liang

Published online: 20 January 2021

DOI: 10.1051/epjn/2020021

EPJ

EPJ Nuclear Sciences & Technologies

Volume 7 (2021)

A tribute to Massimo Salvatores' scientific work

A journey into Massimo Salvatores scientific work E1

Two examples of recent advances in sensitivity calculations 13

Massimo Salvatores: integral experiments and their use for the validation of nuclear data and the neutronic design of advanced nuclear systems 11

Nuclear data assimilation, scientific basis and current status 9

The heuristically-based generalized perturbation theory 7

Fuel Cycle Simulation TWoFCS 2021

Application of sensitivity analysis in DYMOND/Dakota to fuel cycle transition scenarios 26

Development of a MOX equivalence Python code package for ANICCA 25

Pu multi-recycling scenarios towards a PWR fleet for a stabilization of spent fuel inventories in France 23

Enrichment dynamics for advanced reactor HALEU support 22

Estimation of the vitrified canister production for a PWR fleet with the CLASS code 21

Impact of disruption between options of plutonium multi-recycling in PWRs and in SFRs 20

NMB4.0: development of integrated nuclear fuel cycle simulator from the front to back-end 19

Impact of H in H2O thermal scattering data on depletion calculation: k∞, nuclide inventory and decay heat 24

Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat 18

A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors 17

Delayed gamma fraction determination in the zero power reactor CROCUS 16

France–Japan synthesis concept on sodium-cooled fast reactor review of a joint collaborative work 15

Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat 14

Muon radiography to visualise individual fuel rods in sealed casks 12

CONRAD – a code for nuclear data modeling and evaluation 10

A multivariate representation of compressed pin-by-pin cross sections 8

Sea container inspection with tagged neutrons 6

Fission yields and cross sections: correlated or not? 5

Prediction of crack propagation kinetics through multipoint stochastic simulations of microscopic fields 4

VVUQ of a thermal-hydraulic multi-scale tool on unprotected loss of flow accident in SFR reactor 3

A new direction in PWR simplification 2

A simplified analysis of the Chernobyl accident 1

Conference announcements

Impact of H in H₂O thermal scattering data on depletion calculation: k_∞, nuclide inventory and decay heat 24