Publications by Andreas Pautz | EPFL Graph Search

Development of a semi-implicit contact methodology for finite volume stress solvers

Andreas Pautz, Carlo Fiorina, Alessandro Scolaro

The past decades have seen numerous efforts to apply the finite volume methodology to solid mechanics problems. However, only limited work has been done by the finite volume community toward the simulation of mechanical contact. In this article, we present ...

WILEY2021

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

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Andreas Pautz, Jiri Krepel, Fanny Vitullo, Horst-Michael Prasser

In the pebble-bed high-temperature reactor under construction in China, called the HTR-PM, the spherical fuel elements continuously flow downward in the cylindrical core. The burnup of each pebble is checked at the core outlet and, according to the achieve ...

ASME2020

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

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In recent years, Molten Salt Reactors (MSRs), one of the Generation IV concepts, have noticeably gained in interest. Several molten salt reactor types use fuel in liquid form, bringing various advantages, notably in terms of fuel cycle. However, simulating ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

Andreas Pautz, Petra Mala

Currently, the pin-by-pin homogenized solvers are a very active research field as they can, unlike the nodal codes, directly predict the local power, while requiring significantly less computational resources than the heterogeneous transport codes. This pa ...

2020

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

Andreas Pautz, Vincent Pierre Lamirand, Pavel Frajtag, Axel Guy Marie Laureau, Yifeng Jiang

The present article describes the preliminary validation study of simulated in-core and reflector n eutron spectra in preparation of oncoming experimental programs in the zero-power reactor CROCUS at EPFL. For this purpose, a set of activation foils were i ...

E D P SCIENCES2020

Modeling of Quench Protection Concepts for Canted-Cosine-Theta Type High-Field Magnets

Andreas Pautz, Bernhard Auchmann, Jiani Gao

An innovative high-field superconducting magnet of Canted-Cosine-Theta (CCT) type has been proposed for Future Circular Collider 16 T dipole magnet design. The unique mechanical structure intercepts the accumulated forces lowering the stress on the winding ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2020

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

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

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Development of a semi-implicit contact methodology for finite volume stress solvers

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

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

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

Modeling of Quench Protection Concepts for Canted-Cosine-Theta Type High-Field Magnets

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

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

Development of a semi-implicit contact methodology for finite volume stress solvers

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

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Design and Simulation of Gamma Spectrometry Experiments in the CROCUS Reactor

Modeling of Quench Protection Concepts for Canted-Cosine-Theta Type High-Field Magnets

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

Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis

In-core dosimetry for the validation of neutron spectra in the CROCUS reactor

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