Person
Andreas Pautz
Related publications (94)
Computation of sensitivity coefficients in fixed source simulations with SERPENT2
Within the scope of the implementation of a nuclear data pipeline aiming at producing the best possible evaluated nuclear data files, a major point is the production of relevant sensitivity coefficients when including integral benchmark information. Thanks ...
Lausanne2024Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors
Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari
Gamma-ray spectroscopy is an effective technique for radioactive material characterization, routine inventory verification, nuclear safeguards, health physics, and source search scenarios. Gamma-ray spectrometers typically cannot be operated in the immedia ...
MDPI2024Design of an Open-Loop Pile-Oscillation Program in the CROCUS Reactor
Andreas Pautz, Vincent Pierre Lamirand, Thomas Jean-François Ligonnet, Axel Guy Marie Laureau
As a follow-up to the CEA-EPFL PETALE experimental program on stainless steel nuclear data, the EPFL initiated an open-loop pile-oscillation experimental program in the CROCUS reactor: BLOOM. A reproduction of the critical experiments of PETALE, the progra ...
2024Intra-pin Reaction Rate Measurements in the CROCUS Experimental Reactor
Andreas Pautz, Vincent Pierre Lamirand, Mathieu Hursin, Oskari Ville Pakari, Thomas Jean-François Ligonnet, Tom Mager
In response to the need for validating high-fidelity deterministic neutronics solvers capable of providing pin-resolved neutron flux distributions, intra-pin reaction rates measurements were performed in the CROCUS experimental reactor. A specially designe ...
2024Gamma noise to non-invasively monitor nuclear research reactors
Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari, Pavel Frajtag, Tom Mager
Autonomous nuclear reactor monitoring is a key aspect of the International Atomic Energy Agency’s strategy to ensure nonproliferation treaty compliance. From the rise of small modular reactor technology, decentralized nuclear reactor fleets may strain the ...
2024Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators
Andreas Pautz, Vincent Pierre Lamirand, Oskari Ville Pakari
Noise measurements in light water reactor systems aid in generating validation data for integral point kinetic parameter predictions and generating monitoring parameters for reactor safety and safeguards. The CROCUS zero-power reactor has been used to supp ...
Ieee-Inst Electrical Electronics Engineers Inc2024High-Resolution Modeling Without Computation Slowdown for PETALE in CROCUS
Andreas Pautz, Vincent Pierre Lamirand, Thomas Jean-François Ligonnet, Axel Guy Marie Laureau
In a collaboration between Ecole Polytechnique Fédérale de Lausanne (EPFL) and CEA, in the fall of 2020, the experimental Programme d’Étude en Transmission de l’Acier Lourd et ses Eléments (PETALE) was successfully carried out in the CROCUS reactor of EPFL ...
2024Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments
Andreas Pautz, Carlo Fiorina, Alessandro Scolaro, Edoardo Luciano Brunetto
The mechanical analysis of nuclear fuel behavior under base-irradiation conditions has traditionally been performed adopting the small-strain approximation. However, many cases of interest for fuel behavior involve the occurrence of large rod deformations ...
ELSEVIER SCIENCE SA2023Analysis of the preliminary campaign for the PETALE program
Andreas Pautz, Vincent Pierre Lamirand, Thomas Jean-François Ligonnet, Axel Guy Marie Laureau
The PETALE program aims to provide new experimental data to constrain the stainless steel nuclear data. In this frame, a preliminary measurement campaign has been performed to characterize the neutron flux in key positions of the CROCUS reactor and to deve ...
EDP SCIENCES S A2023Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver
Andreas Pautz, Carlo Fiorina, Thomas Arthur Louis Joseph Guilbaud
This work presents a preliminary safety analysis of the accelerator-driven system under development at TRANSMUTEX. It is a sub-critical lead-cooled fast reactor with a nominal power of 300 MWth having the following features: (1) an inert-matrix fuel; (2) a ...
Oxford2023