Publications related to Testing of a sCVD diamond detection system in the CROCUS reactor

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

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

Experimental and numerical study of stochastic branching noise in nuclear reactors

Oskari Ville Pakari

Noise analysis applied to nuclear reactor physics is a powerful tool to investigate a reactor's kinetic parameters, and more generally underlying physical processes determining core behavior. The kinetic parameters are the coefficients of simplified time-d ...

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

GEN-FOAM: An OpenFOAM (R)-Based Multi-physics Solver for Nuclear Reactor Analysis

Carlo Fiorina

A multi-physics solver for nuclear reactor analysis, named GeN-Foam (Generalized Nuclear Foam), has been developed by the Laboratory for Reactor Physics and System Behavior at the EPFL and at the Paul Scherrer Institut (Switzerland). The developed solver c ...

SPRINGER INTERNATIONAL PUBLISHING AG2019

Reactor simulations with nuclear data uncertainties

Andreas Pautz, Winfried Zwermann, Friederike Bostelmann, Alexander Aures

The paper demonstrates the influence of uncertainties in microscopic nuclear data on the results of reactor simulations, both for stationary and transient states. It gives an overview on the methods in use for uncertainty and sensitivity analyses with resp ...

ELSEVIER SCIENCE SA2019

Transient fission matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations

Axel Guy Marie Laureau

CEA is currently working on a new ZPR called ZEPHYR (Zero power Experimental PHYsics Reactor), to be built on the Cadarache Center in the next decade. Its awaited experimental capacities should go well beyond traditional needs, and in particular extended p ...

PERGAMON-ELSEVIER SCIENCE LTD2019

EU DEMO EC system preliminary conceptual design

Stefano Alberti, Minh Quang Tran, Ioannis Pagonakis, Emanuele Poli, Konstantinos Avramidis

The engineering design and R&D of auxiliary heating systems and their sub-systems are a key activities in the frame of the present conceptual design phase for a first of a kind DEMOnstration Fusion Power Plant in order to develop a system capable of achiev ...

ELSEVIER SCIENCE SA2018

CROCUS Concrete Activation Study by γ-ray Spectrometry and TLD Neutron Flux Measurements

Isabelle Tanseri

The semester project was under the course Physics lab IVb at EPFL. At EPFL site, the experimental fission reactor CROCUS is shielded by concrete which becomes radioactive as a result of neutron interaction. The activation is of interest to study for valida ...

2017

Testing of a sCVD diamond detection system in the CROCUS reactor

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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

Experimental and numerical study of stochastic branching noise in nuclear reactors

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

GEN-FOAM: An OpenFOAM (R)-Based Multi-physics Solver for Nuclear Reactor Analysis

Reactor simulations with nuclear data uncertainties

Transient fission matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations

EU DEMO EC system preliminary conceptual design

CROCUS Concrete Activation Study by γ-ray Spectrometry and TLD Neutron Flux Measurements

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

Experimental and numerical study of stochastic branching noise in nuclear reactors

GEN-FOAM: An OpenFOAM (R)-Based Multi-physics Solver for Nuclear Reactor Analysis

CROCUS Concrete Activation Study by γ-ray Spectrometry and TLD Neutron Flux Measurements

EU DEMO EC system preliminary conceptual design

Reactor simulations with nuclear data uncertainties

Transient fission matrix approach for assessing complex kinetics behavior in the ZEPHYR ZPR coupled core configurations