Publications related to Performance assessment of a 3-D steady-state and spatial kinetics model for the CROCUS reactor

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

The Unscented Kalman Filter: Introduction and Application to Point Reactor Kinetics

Felix Hans Michel Grimberg

This report serves two purposes. The first is to introduce the linear Kalman filter and the unscented Kalman filter to readers who are unfamiliar with either or both. To this end, it contains an extensive explanation of these methods, including all equatio ...

2020

Breed-and-burn fuel cycle in molten salt reactors

Andreas Pautz, Jiri Krepel, Boris Aviv Hombourger

The operation of a reactor on an open but self-sustainable cycle without actinide separation is known as breed-and-burn. It has mostly been envisioned for use in solid-fueled fast-spectrum reactors such as sodium-cooled fast reactors. In this paper the app ...

EDP Sciences2019

Towards the validation of neutron noise simulators: qualification of data acquisition systems

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Axel Guy Marie Laureau, Adolfo Rais

This paper deals with the processes involved in the generation of reliable experimental data for the validation of computer simulations. In the field of neutron noise, the analysis of results is based on spectral features of the detector signals in the fre ...

2019

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

Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Pavel Frajtag, Daniel Godat

This article presents the results of an experimental campaign in the CROCUS zero power reactor aimed at investigating the spatial effects of neutron noise measurements. Neutron noise measurements offer a non-invasive method to determine kinetic reactor par ...

American Nuclear Society2018

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

Andreas Pautz, Konstantin Mikityuk, Carlo Fiorina, Stefan Radman

The current work presents a simplified benchmark for a pool-type Sodium Fast Reactor based on a 2D (r-z) geometry for testing tightly-coupled spatial neutron transport, thermal-hydraulics and thermal-mechanics modeling. The new benchmark is motivated by de ...

AMER SOC MECHANICAL ENGINEERS2018

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

Creation Of An Openfoam Fuel Performance Class Based On Fred And Integration Into The Gen-Foam Multi-Physics Code

Andreas Pautz, Konstantin Mikityuk, Carlo Fiorina

The FRED code is an in-house tool developed at the Paul Scherrer Institut for the so-called 1.5-D nuclear fuel performance analysis. In order to extend its field of application, this code has been re-implemented as a class of the OpenFOAM numerical library ...

AMER SOC MECHANICAL ENGINEERS2018

Design of Separated Element Reflector Experiments in CROCUS: PETALE

Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Pavel Frajtag, Daniel Jerôme Siefman

The present article describes the preliminary design studies for PETALE (Programme d'Etude en Transmission de l'Acier Lourd et ses Elements), an oncoming experimental program in the CROCUS reactor. Within the framework of the Venus-Eole-Proteus collaborati ...

ASTM INTERNATIONAL2018

Performance assessment of a 3-D steady-state and spatial kinetics model for the CROCUS reactor

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

The Unscented Kalman Filter: Introduction and Application to Point Reactor Kinetics

Breed-and-burn fuel cycle in molten salt reactors

Towards the validation of neutron noise simulators: qualification of data acquisition systems

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

Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

EU DEMO EC system preliminary conceptual design

Creation Of An Openfoam Fuel Performance Class Based On Fred And Integration Into The Gen-Foam Multi-Physics Code

Design of Separated Element Reflector Experiments in CROCUS: PETALE

Design of Separated Element Reflector Experiments in CROCUS: PETALE

Breed-and-burn fuel cycle in molten salt reactors

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

Towards the validation of neutron noise simulators: qualification of data acquisition systems

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

Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS

EU DEMO EC system preliminary conceptual design

Creation Of An Openfoam Fuel Performance Class Based On Fred And Integration Into The Gen-Foam Multi-Physics Code

The Unscented Kalman Filter: Introduction and Application to Point Reactor Kinetics

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors