EPJ Nuclear Sciences & Technologies

Open Access

Regular Article

Compendium on Monte Carlo simulation of photoneutrons in the Giant Dipole Resonance energy range

Louis Garnaud, Luna Sobczak, Johann Piekar, Adrien Sari, Alexis Jinaphanh, Cédric Jouanne, Amine Nasri, Tatsuhiko Ogawa and Andrea Zoia

Published online: 30 January 2026

DOI: 10.1051/epjn/2025078

Open Access

Regular Article

Development of an adjoint flux calculation technique for exact perturbation theory in Monte Carlo transport

Yunki Jo and Deokjung Lee

Published online: 16 January 2026

DOI: 10.1051/epjn/2025068

Open Access

Regular Article

Adaptive adjoint-based population-control methods for kinetic simulations in TRIPOLI-4

Cecilia Montecchio, Davide Mancusi, Vincent Lamirand, Wilfried Monange and Andrea Zoia

Published online: 21 November 2025

DOI: 10.1051/epjn/2025069

Open Access

Regular Article

Convergence of Monte Carlo algorithms for power reactor noise

Axel Fauvel, Amélie Rouchon, Davide Mancusi and Andrea Zoia

Published online: 06 November 2025

DOI: 10.1051/epjn/2025062

Open Access

Regular Article

Sensitivity and uncertainty calculations in support of the noise analysis of the TAPIRO reactor

Alex Aimetta and Sandra Dulla

Published online: 05 November 2025

DOI: 10.1051/epjn/2025065

Open Access

Regular Article

Simulating hydrogen diffusion in a zirconium hydride moderator block and its impact on steady state neutronic-thermal behavior

William R. Kendrick and Benoit Forget

Published online: 20 October 2025

DOI: 10.1051/epjn/2025057

Open Access

Regular Article

New model developments for fuel supply strategies in molten salt reactors: Application to the REM depletion code

Louiliam Clot, Elsa Merle, Axel Laureau, Daniel Heuer, Léa Tillard and Gérald Senentz

Published online: 20 October 2025

DOI: 10.1051/epjn/2025063

Open Access

Regular Article

Overview of kinetic Monte Carlo methods used to simulate microstructural evolution of materials under irradiation

Gilles Adjanor, Rohit Vasav, Thomas Jourdan, Christophe Domain, Normand Mousseau, Md Mijanur Rahman and Manuel Athènes

Published online: 20 October 2025

DOI: 10.1051/epjn/2025064

Open Access

Regular Article

Extending Embedded Monte Carlo as a novel method for nuclear data uncertainty quantification

Gregoire Biot, Pablo Ducru, Vladimir Sobes, Amanda Lewis and Benoit Forget

Published online: 08 October 2025

DOI: 10.1051/epjn/2025052

Open Access

Regular Article

Accelerating split-exponential track length estimator on GPU for Monte Carlo simulations

Henri Hutinet, Pierre-Louis Antonsanti, Cindy Le Loirec and Davide Mancusi

Published online: 08 October 2025

DOI: 10.1051/epjn/2025053

Open Access

Regular Article

Multi-output Gaussian processes for the reconstruction of homogenized cross-sections

Olivier Truffinet, Karim Ammar, Jean-Philippe Argaud, Nicolas Gérard Castaing and Bertrand Bouriquet

Published online: 01 October 2025

DOI: 10.1051/epjn/2025055

Open Access

Regular Article

Derivation and verification of the direct-sampling method for simulating Monte Carlo flight paths in tetrahedral meshes with linear finite-element cross sections

Pablo A. Vaquer, Michael E. Rising, Joel A. Kulesza and Colin A. Weaver

Published online: 30 September 2025

DOI: 10.1051/epjn/2025051

Open Access

Regular Article

Data-driven reduced order modelling with malfunctioning sensors recovery applied to the Molten Salt Reactor case

Stefano Riva, Carolina Introini, Enrico Zio and Antonio Cammi

Published online: 16 September 2025

DOI: 10.1051/epjn/2025054

Open Access

Regular Article

Advanced reactor models for plutonium multirecycling scenario studies using artificial neural networks

Sarah Eveillard, Fanny Courtin, Xavier Doligez, Marc Ernoult, Nicolas Thiollière, Kévin Tirel and Jean-François Vidal

Published online: 12 September 2025

DOI: 10.1051/epjn/2025049

Open Access

Regular Article

TRUST: the HPC open-source CFD platform – from CPU to GPU

Elie Saikali, Adrien Bruneton, Pierre Ledac and Remi Bourgeois

Published online: 22 September 2025

DOI: 10.1051/epjn/2025050

Open Access

Regular Article

Neutronics and thermal hydraulics analysis on a Lead-bismuth-cooled fast reactor

Chunyuan Liu, Xiaosong Chen, Eing Yee Yeoh, Linsen Li and Yueting Xiao

Published online: 03 September 2025

DOI: 10.1051/epjn/2025043

Open Access

Regular Article

Fundamental properties and characteristics of flux distribution tallies using proper orthogonal decomposition

Ryoichi Kondo, Akio Yamamoto and Tomohiro Endo

Published online: 04 June 2025

DOI: 10.1051/epjn/2025019

EPJ

EPJ Nuclear Sciences & Technologies

Special Issue on ‘Overview of recent advances in HPC simulation methods for nuclear applications’, edited by Andrea Zoia, Elie Saikali, Cheikh Diop and Cyrille de Saint Jean

Compendium on Monte Carlo simulation of photoneutrons in the Giant Dipole Resonance energy range

Development of an adjoint flux calculation technique for exact perturbation theory in Monte Carlo transport

Adaptive adjoint-based population-control methods for kinetic simulations in TRIPOLI-4

Convergence of Monte Carlo algorithms for power reactor noise

Sensitivity and uncertainty calculations in support of the noise analysis of the TAPIRO reactor

Simulating hydrogen diffusion in a zirconium hydride moderator block and its impact on steady state neutronic-thermal behavior

New model developments for fuel supply strategies in molten salt reactors: Application to the REM depletion code

Overview of kinetic Monte Carlo methods used to simulate microstructural evolution of materials under irradiation

Extending Embedded Monte Carlo as a novel method for nuclear data uncertainty quantification

Accelerating split-exponential track length estimator on GPU for Monte Carlo simulations

Multi-output Gaussian processes for the reconstruction of homogenized cross-sections

Derivation and verification of the direct-sampling method for simulating Monte Carlo flight paths in tetrahedral meshes with linear finite-element cross sections

Data-driven reduced order modelling with malfunctioning sensors recovery applied to the Molten Salt Reactor case

Advanced reactor models for plutonium multirecycling scenario studies using artificial neural networks

TRUST: the HPC open-source CFD platform – from CPU to GPU

Neutronics and thermal hydraulics analysis on a Lead-bismuth-cooled fast reactor

Fundamental properties and characteristics of flux distribution tallies using proper orthogonal decomposition

Conference announcements