Publications related to Assessment of mechanical properties in unirradiated and irradiated zircaloys and steels with non-standard tests and finite element calculations

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Fanny Vitullo

Gamma rays in nuclear reactors, arising either from fission or decay processes, significantly contribute to the heating and dose of the reactor components. Zero power research reactors offer the possibility to measure gamma rays in a purely neutronic envir ...

E D P SCIENCES2020

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

László Forró, Endre Horvath, Andrzej Sienkiewicz, Bálint Náfrádi, Márton Kollár, Pavao Roko Andricevic

Detection and direct power conversion of high energy and high intensity ionizing radiation could be a key element in next generation nuclear reactor safety systems and space-born devices. For example, the Fukushima catastrophe in 2011 could have been large ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Dynamic study of contact damping in martensitic stainless steels using nano-indentation

Philippe Spätig, Hans-Peter Seifert

The study was undertaken to gain insight into the micro-mechanisms controlling plasticity at the micrometer scale of elastic-plastic metallic alloys. Dynamic nano-indentation tests, where a small harmonic force amplitude is superimposed during loading, ref ...

ELSEVIER2020

Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

Friederike Bostelmann

Sodium-cooled fast reactor (SFR) technologies have the potential to guarantee energy supply and to reduce the burden of nuclear waste for future generations. For an adequate simulation of these reactor systems, well-established tools that have so far been ...

EPFL2020

A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS

Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari, Pavel Frajtag, Fanny Vitullo, Jean-Baptiste Mosset

This article presents the development, full-characterization, and in-core testing of a miniature neutron detector for the investigation of highly localized in-core neutronics effects in the zero-power reactor CROCUS, operated at the Ecole Polytechnique fed ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2020

Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Carlo Fiorina, Oskari Ville Pakari, Pavel Frajtag, Daniel Godat, Axel Guy Marie Laureau, Adolfo Rais

The present article gives an overview of the first experimental campaigns carried out in the AKR-2 and CROCUS reactors within the framework of the Horizon 2020 European project CORTEX. CORTEX aims at developing innovative core monitoring techniques that al ...

E D P SCIENCES2020

Review of kinetic modulation experiments in low power nuclear reactors

Vincent Pierre Lamirand

The safety improvement of nuclear reactors requires continuous efforts in understanding the fundamental physical quantities related to the fission process. In neutronic models, the reactor dynamics is covered by the kinetic parameters to characterize the t ...

2020

Experimental evaluation and modeling of fatigue of a 316L austenitic stainless steel in high-temperature water and air environments

Wen Chen

Austenitic stainless steels is used in many components of nuclear power plants, particularly in the pipes of cooling systems. Owing to power transients and to start-ups and shutdowns, these components are subjected to thermo-mechanical loadings (low-cycle ...

EPFL2020

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

Andreas Pautz, Winfried Zwermann, Alexander Aures

The impact of nuclear data uncertainties is studied for the reactor power and the reactivity during control rod withdrawal transients with reactivity insertions of 0.5

and 0.97

, respectively, for a PWR mini-core model. Multi-group cross sections, the mul ...

PERGAMON-ELSEVIER SCIENCE LTD2020

SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

Andreas Pautz, Winfried Zwermann, Friederike Bostelmann

New multigroup cross section libraries and associated covariance files that are optimized for the analysis of sodium-cooled fast reactors were generated with the AMPX tools distributed with the SCALE code system. These new libraries account for the fast ne ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Assessment of mechanical properties in unirradiated and irradiated zircaloys and steels with non-standard tests and finite element calculations

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Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

Dynamic study of contact damping in martensitic stainless steels using nano-indentation

Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS

Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

Review of kinetic modulation experiments in low power nuclear reactors

Experimental evaluation and modeling of fatigue of a 316L austenitic stainless steel in high-temperature water and air environments

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

Dynamic study of contact damping in martensitic stainless steels using nano-indentation

Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits

SCALE/AMPX multigroup libraries for sodium-cooled fast reactor systems

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX

A mm(3) Fiber-Coupled Scintillator for In-Core Thermal Neutron Detection in CROCUS

Review of kinetic modulation experiments in low power nuclear reactors

Experimental evaluation and modeling of fatigue of a 316L austenitic stainless steel in high-temperature water and air environments