Journal

Kerntechnik

2195-8580 · Walter de Gruyter GmbH

103 verified public works

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The heat pipe, the microreactor, and the space

2026 · 0 citations

Evaluating heat pipe technologies for nuclear cooling: from terrestrial spent fuel pools to space-based reactors

2026 · 0 citations

Electric space propulsion at the Institute of Space Systems Stuttgart: from low-power to high-power for nuclear electric propulsion applications

2026 · 0 citations

Burnup calculations using serpent code in accelerator driven thorium reactors

2013 · 0 citations

Albedo and constant source problems for extremely anisotropic scattering

2013 · 0 citations

T N approximation for the critical size of one-speed neutrons in a slab with anisotropic scattering

2013 · 0 citations

Computational modeling of monoenergetic neutral particle inverse transport problems in slab geometry

2013 · 0 citations

Analytical study on degraded core quenching

2013 · 0 citations

Experimental investigations on control of flow instability in single-phase natural circulation loop

2013 · 0 citations

CFD analysis of passive autocatalytic recombiner interaction with atmosphere

2011 · 0 citations

Summaries

2010 · 0 citations

Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method

2010 · 0 citations

Algorithmic determination of fuel rod cladding burst time at elevated temperatures

2010 · 0 citations

Summaries

2010 · 0 citations

The boundary problem in the 1D-CANDLE burn-up reactor

2010 · 0 citations

An analytical solution for the one-dimensional time-dependent S N transport equation for bounded and unbounded domains in cartesian geometry

2010 · 0 citations

Neutron transmutation doping conceptual design

2010 · 0 citations

Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering

2010 · 0 citations

Heat transfer to the building structures of the Ignalina NPP accident localisation system

2010 · 0 citations

Development of a decommissioning strategy for the MR research reactor

2010 · 0 citations

Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization

2010 · 0 citations

Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor

2010 · 0 citations

Summaries

2010 · 0 citations

Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients

2010 · 0 citations

Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry

2010 · 0 citations

European clearinghouse on nuclear power plants operational experience feedback

2010 · 0 citations

A model for calculation of forward isotropic scattering with application to transport equation in slab geometry

2009 · 0 citations

Kerntechnik

The heat pipe, the microreactor, and the space

Evaluating heat pipe technologies for nuclear cooling: from terrestrial spent fuel pools to space-based reactors

Electric space propulsion at the Institute of Space Systems Stuttgart: from low-power to high-power for nuclear electric propulsion applications

Burnup calculations using serpent code in accelerator driven thorium reactors

Albedo and constant source problems for extremely anisotropic scattering

T N approximation for the critical size of one-speed neutrons in a slab with anisotropic scattering

Computational modeling of monoenergetic neutral particle inverse transport problems in slab geometry

Analytical study on degraded core quenching

Experimental investigations on control of flow instability in single-phase natural circulation loop

CFD analysis of passive autocatalytic recombiner interaction with atmosphere

Summaries

Analysis of the instability of OTSG of movable nuclear power devices by using the multivariable frequency domain method

Algorithmic determination of fuel rod cladding burst time at elevated temperatures

Summaries

Contents

The boundary problem in the 1D-CANDLE burn-up reactor

An analytical solution for the one-dimensional time-dependent S N transport equation for bounded and unbounded domains in cartesian geometry

Neutron transmutation doping conceptual design

Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering

Heat transfer to the building structures of the Ignalina NPP accident localisation system

Contents

Development of a decommissioning strategy for the MR research reactor

Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization

Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor

Summaries

Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients

Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry

European clearinghouse on nuclear power plants operational experience feedback

A model for calculation of forward isotropic scattering with application to transport equation in slab geometry

Contents