Journal

Kerntechnik

2195-8580 · Walter de Gruyter GmbH

103 verified public works

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Numerical simulation of passive catalytic recombiner

2009 · 0 citations

Training and retraining programme for research reactor operating personnel

2009 · 0 citations

Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)

2009 · 0 citations

Legendre polynomial series of the infinite medium Green's Function in neutral particle transport theory: the half-space albedo problem

2009 · 0 citations

Some affine solutions for CANDLE burn-up waves in 1D-geometry

2009 · 0 citations

Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison

2009 · 0 citations

CFD modelling of insulation debris transport phenomena in water flow

2009 · 0 citations

Assessment of radiological consequences due to routine atmospheric discharges from nuclear power plants

2009 · 0 citations

Prediction of time dependent standby failure rates for periodically tested components taking into account the operational history

2009 · 0 citations

Summaries

2009 · 0 citations

Chebyshev acceleration of criticality calculations in boundary element applications to neutron diffusion

2009 · 0 citations

Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS)

2009 · 0 citations

Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes

2009 · 0 citations

Non-destructive measuring techniques for on-site detection and identification of illicit nuclear material

2009 · 0 citations

The Open PSA Initiative for next generation probabilistic safety assessment

2009 · 0 citations

Consideration of ageing within probabilistic safety assessment models and results

2009 · 0 citations

Methodology for Fire PSA during design process

2009 · 0 citations

The new IAEA safety standards on probabilistic safety assessment

2009 · 0 citations

Implementation of decision support systems in Austria

2007 · 0 citations

The revised program for measurements in intense operation mode according to AVV-IMIS

2007 · 0 citations

Modeling of the TOSQAN test facility with the lumped parameter code COCOSYS

2006 · 0 citations

Summaries

2006 · 0 citations

Modelling of the cumulative behaviour of Caesium and Strontium activities in nuclear fuel

2006 · 0 citations

Analytical study of the closure flow inside the ETRR-2 core chimney

2006 · 0 citations

Milne problem for isotropic and linearly anisotropic scattering for specular and diffuse reflecting boundary conditions solved with the HN method

2006 · 0 citations

Thermal-hydraulic modeling of the onset of flow instability in MTR reactors

2006 · 0 citations

Minimizing radiation exposure for the reactor staff during the dismantling of a TRIGA research reactor

2006 · 0 citations

Minor actinide burning in a CANDU thorium reactor

2006 · 0 citations

ICDE-results on complete common cause failures in the light of results obtained with the POS model

2006 · 0 citations

Kerntechnik

Numerical simulation of passive catalytic recombiner

Training and retraining programme for research reactor operating personnel

Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)

Legendre polynomial series of the infinite medium Green's Function in neutral particle transport theory: the half-space albedo problem

Some affine solutions for CANDLE burn-up waves in 1D-geometry

Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison

CFD modelling of insulation debris transport phenomena in water flow

Assessment of radiological consequences due to routine atmospheric discharges from nuclear power plants

Prediction of time dependent standby failure rates for periodically tested components taking into account the operational history

Summaries

Chebyshev acceleration of criticality calculations in boundary element applications to neutron diffusion

Main results of the European project NURESIM on the CFD-modelling of two-phase Pressurized Thermal Shock (PTS)

Simulation of H2 distribution and combustion in LWR containments using Lumped Parameter Codes

Non-destructive measuring techniques for on-site detection and identification of illicit nuclear material

The Open PSA Initiative for next generation probabilistic safety assessment

Consideration of ageing within probabilistic safety assessment models and results

Methodology for Fire PSA during design process

The new IAEA safety standards on probabilistic safety assessment

Implementation of decision support systems in Austria

The revised program for measurements in intense operation mode according to AVV-IMIS

Modeling of the TOSQAN test facility with the lumped parameter code COCOSYS

Summaries

Modelling of the cumulative behaviour of Caesium and Strontium activities in nuclear fuel

Analytical study of the closure flow inside the ETRR-2 core chimney

Milne problem for isotropic and linearly anisotropic scattering for specular and diffuse reflecting boundary conditions solved with the HN method

Thermal-hydraulic modeling of the onset of flow instability in MTR reactors

Minimizing radiation exposure for the reactor staff during the dismantling of a TRIGA research reactor

Minor actinide burning in a CANDU thorium reactor

Contents

ICDE-results on complete common cause failures in the light of results obtained with the POS model