Open Access
Editorial
Advances in the physics and thermohydraulics of nuclear reactors
Published online: 16 August 2021
DOI: 10.1140/epjp/s13360-021-01391-2
EPJ Plus
Focus Point on Advances in the Physics and Thermohydraulics of Nuclear Reactors
J. Ongena, P. Ravetto, M. Ripani and P. Saracco
Coupled 3D thermal–hydraulic and neutron kinetic Relap5 model for transient analysis of a 1200-MWe nuclear PWR plant
Published online: 14 September 2020
DOI: 10.1140/epjp/s13360-020-00628-w
Open Access
Erratum
Erratum to: A Serpent/OpenFOAM coupling for 3D burnup analysis
Published online: 26 June 2020
DOI: 10.1140/epjp/s13360-020-00519-0
A Serpent/OpenFOAM coupling for 3D burnup analysis
Published online: 22 July 2020
DOI: 10.1140/epjp/s13360-020-00427-3
A multiphysics model for analysis of inert gas bubbles in Molten Salt Fast Reactor
Published online: 19 May 2020
DOI: 10.1140/epjp/s13360-020-00428-2
A re-visitation of space asymptotic theory in neutron transport
Published online: 06 April 2020
DOI: 10.1140/epjp/s13360-020-00324-9
A coupled neutronic and thermal-hydraulic model for ALFRED
Published online: 24 March 2020
DOI: 10.1140/epjp/s13360-020-00328-5
Open Access
Simulation of a research reactor reactivity transient with deterministic and GPU-assisted Monte Carlo reactor kinetics codes
Published online: 02 March 2020
DOI: 10.1140/epjp/s13360-020-00280-4
Subcriticality estimation by extended Kalman filter technique in transient experiment with external neutron source at Kyoto University Critical Assembly
Published online: 18 February 2020
DOI: 10.1140/epjp/s13360-020-00270-6
Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors
Published online: 10 February 2020
DOI: 10.1140/epjp/s13360-020-00171-8
High-accuracy neutron diffusion calculations based on integral transport theory
Published online: 10 February 2020
DOI: 10.1140/epjp/s13360-020-00216-y
Coarse-mesh thermal-hydraulics and neutronics coupling for the ALFRED reactor
Published online: 04 February 2020
DOI: 10.1140/epjp/s13360-020-00228-8
Stabilization of the stochastic point reactor kinetic equation through power feedback
Published online: 03 February 2020
DOI: 10.1140/epjp/s13360-020-00215-z
On the boundary conditions for the neutron transport equation
Published online: 28 January 2020
DOI: 10.1140/epjp/s13360-020-00193-2
Numerical simulations of an innovative decay heat removal systems
Published online: 28 January 2020
DOI: 10.1140/epjp/s13360-020-00214-0
Benchmarking of MANCINTAP 2.0, a parallel high-performance tool for neutron activation analysis in complex 4D scenarios
Published online: 23 January 2020
DOI: 10.1140/epjp/s13360-020-00162-9
Design of an accelerator-driven subcritical dual fluid reactor for transmutation of actinides
Published online: 05 December 2019
DOI: 10.1140/epjp/i2019-13015-3
Extension of the “42-0” approach to ternary fuels and application to a thorium-fed, minor-actinides-burner ADS
Published online: 04 December 2019
DOI: 10.1140/epjp/i2019-13014-4
