Journal

Kerntechnik

2195-8580 · Walter de Gruyter GmbH

103 verified public works

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Neutron transport problems for extremely anisotropic scattering

2006 · 0 citations

Radiation transfer in inhomogeneous exponential media

2006 · 0 citations

Determination of the exposure build-up factor in a slab using the LTSN method

2006 · 0 citations

Lumped parameters analysis of the IAEA research reactor benchmark problem

2006 · 0 citations

Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant

2006 · 0 citations

A finite element model for static strength analysis of CANDU fuel bundle

2006 · 0 citations

Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV

2006 · 0 citations

Analyses of severe accident scenarios in RBMK-1500

2006 · 0 citations

Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor

2006 · 0 citations

Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors

2006 · 0 citations

The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results

2006 · 0 citations

Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects

2006 · 0 citations

Summaries

2006 · 0 citations

Performance analyses of the pool-top radiation level reduction systems at the ETRR-2 research reactor

2006 · 0 citations

Irradiation damages in tantalum spallation target

2006 · 0 citations

Multigroup neutron reflection and leakage conditions for axial core models with anisotropic scattering

2006 · 0 citations

Experimental investigation and CFD simulation of horizontal air/water slug flow

2006 · 0 citations

An interpretation procedure for the purpose of incorporation monitoring during decommissioning of nuclear reactors

2006 · 0 citations

Uncertainty and sensitivity analysis of the CPS-CC voiding in the RBMK reactor Ignalina-2

2006 · 0 citations

Summaries

2006 · 0 citations

Experiments and comparing calculations on thermohydraulic pressure surges in pipes

2006 · 0 citations

Thermal hydraulics of the fixed bed nuclear reactor concept

2006 · 0 citations

The critical slab problem for linearly anisotropic scattering and reflecting boundary conditions with the HN method

2006 · 0 citations

Current use of probabilistic safety evaluations for advanced reactor concepts

2006 · 0 citations

Extension of the German database for common cause failure events

2006 · 0 citations

Protection against dependent failures, analysis of dependencies and derivation of CCF data

2006 · 0 citations

The Process-Oriented Simulation (POS) model for common cause failures: recent progress

2006 · 0 citations

Kerntechnik

Neutron transport problems for extremely anisotropic scattering

Radiation transfer in inhomogeneous exponential media

Contents

Determination of the exposure build-up factor in a slab using the LTSN method

Lumped parameters analysis of the IAEA research reactor benchmark problem

Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant

A finite element model for static strength analysis of CANDU fuel bundle

Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV

Analyses of severe accident scenarios in RBMK-1500

Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor

Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors

The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results

Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects

Summaries

Performance analyses of the pool-top radiation level reduction systems at the ETRR-2 research reactor

Irradiation damages in tantalum spallation target

Multigroup neutron reflection and leakage conditions for axial core models with anisotropic scattering

Experimental investigation and CFD simulation of horizontal air/water slug flow

An interpretation procedure for the purpose of incorporation monitoring during decommissioning of nuclear reactors

Uncertainty and sensitivity analysis of the CPS-CC voiding in the RBMK reactor Ignalina-2

Summaries

Experiments and comparing calculations on thermohydraulic pressure surges in pipes

Thermal hydraulics of the fixed bed nuclear reactor concept

The critical slab problem for linearly anisotropic scattering and reflecting boundary conditions with the HN method

Contents

Current use of probabilistic safety evaluations for advanced reactor concepts

Extension of the German database for common cause failure events

Protection against dependent failures, analysis of dependencies and derivation of CCF data

The Process-Oriented Simulation (POS) model for common cause failures: recent progress

Contents