Publications by Andreas Pautz | EPFL Graph Search

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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 ...

To respond to the needs of the future accelerators and the upgrade of existing machines, superconducting magnet technology is continuously evolving in the direction of high fields and high current densities. As a result, a fast and efficient quench detecti ...

This paper presents the development and application of an event tracking feature within the OpenMC Monte Carlo code, designed for advanced neutron spectroscopy and scatter camera system simulations. The newly implemented feature enables the tracking of ind ...

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 ...

Data assimilation methods have recently been implemented in the sensitivity analysis and uncertainty quantification tool SHARK-X. This paper presents how they were used with sensitivity coefficients and randomly-sampled nuclear data to simulate integral pa ...

Measurements of scalar flux distributions with fine spatial and energy resolutions are needed to remedy one of the validation shortcomings of the novel neutronics full core solvers, such as MPACT and nTRACER. While a very detailed resolution of the flux ca ...

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 ...

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 ...

This paper reports the methodology used for the neutronic modelling of the CROCUS reactor and discusses the challenges encountered during the process. Full-core steady-state neutronics solutions were computed with the PARCS code. The Serpent Monte Carlo co ...

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 ...

The EPFL and the PSI have been developing in recent years a new fuel performance tool named OFFBEAT. The tool is based on the OpenFOAM finite-volume library and allows for 1.5-D, 2-D and 3-D fuel performance analyses, both for base irradiation and for tran ...

OFFBEAT is a 1D, 2D and 3D fuel behavior code under development at the École Polytechnique Fédérale de Lausanne (EPFL) and the Paul Scherrer Institute (PSI). In this paper, an incremental stress-strain solver with dynamic mesh update is presented and preli ...

We measured the prompt neutron decay constant

\alpha

alpha of the CROCUS zero-power reactor at the Swiss Federal Institute of Technology Lausanne using cross-power spectral density (CPSD) analysis of gamma-gamma correlations from two trans-stilbene org ...

In the work presented in this paper, a sensitivity analysis using the Morris screening method was carried out for a model of the Flooding Experiment with Blocked Arrays (FEBA) separate-effect test facility. The sensitivity analysis was conducted in the con ...

The systematic use of high-fidelity high-resolution codes which allow the prediction of safety parameters on a local scale, can result in more efficient use of the nuclear fuel and of the nuclear reactor.The Laboratory of Reactor Physics and Thermal-Hydrau ...

The FMI is a standard that defines a container and an interface to exchange dynamic simulation models. It has been developed and refined by several actors over the past two decades. This coupling standard allows seamless integrations of independent objects ...

In the framework of an international collaboration, the critical decay constant (α0 = β/Λ), and delayed neutron fraction (β) of the CROCUS reactor were measured by teams of EPFL/PSI, CEA and SCK•CEN research institutes using the Rossi-α and Power Spectral ...

Nuclear reactors are stochastic systems, in which several parameters fluctuate even during steady-state conditions. In addition, structural components like fuel assemblies, vibrate due to strong hydraulic forces. This stochasticity is the cause of the neut ...

We present the experimental campaigns – namely, three per facility – carried out between 2018 and 2021 in the AKR–2 and CROCUS zero power reactors within the framework of the Horizon 2020 European project CORTEX. Their purpose was to produce high-quality a ...

Causality analysis is a substantial tool for identifying cause-and-effect links between different components of a system and has been extensively used in various areas of science such as neuroscience, climatology, and econometrics. This analysis is carried ...

Andreas Pautz

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A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

Study of a Current-Based Quench Detection Method for CCT Magnets via a Co-Wound Superconducting Sensing Wire

Development of an Event Tracking Feature in OpenMC for Neutron Spectroscopy and Scatter Camera Systems

Analysis of the preliminary campaign for the PETALE program

Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments

Development of a High Fidelity Model of the CROCUS Experimental Reactor

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

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

Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Bayesian Data Assimilation for Fuel Performance based on OFFBEAT

Development in OFFBEAT of a dynamic-mesh incremental stress-strain solver and validation against the IFA 650.2 ballooning experiment

Welch Method and Bootstrapping Applied to Subcritical Gamma Noise

Sensitivity Analysis of a Bottom Reflood Simulation using Morris Screening Method

Multi-physics Sub-pin Resolution Analysis of a PWR core with nTRACER/CTF for the OECD/NEA TVA Watts Bar 1 Benchmark

Investigating the Functional Mock-up Interface as a Coupling Framework for the multi-fidelity analysis of nuclear reactors

Intercomparison of neutron noise measurement systems in the CROCUS reactor

Development and verification of a methodology for neutron noise response to fuel assembly vibrations

CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes

Application of causality analysis on nuclear reactor systems