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Andreas Pautz

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Related publications (121)

Kinetic Parameter Measurements in the CROCUS Reactor Using Current Mode Instrumentation

Pavel Frajtag, Andreas Pautz, Oskari Ville Pakari, Vincent Pierre Lamirand

This paper is an overview of developments and results regarding neutron noise measurements in current mode at the CROCUS zero power facility. Neutron noise measurements offer a noninvasive method to determine kinetic reactor parameters such as the prompt d ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2018

A reduced order accelerator for time-dependent segregated neutronic solvers

Andreas Pautz, Alessandro Scolaro, Stefan Radman, Carlo Fiorina

The deterministic solution of the neutron transport problem entails the coupled solution of several partial differential equations, one for each energy group, direction and/or spherical harmonic. Several techniques have been devised for accelerating the so ...

PERGAMON-ELSEVIER SCIENCE LTD2018

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

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

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

Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor

Andreas Pautz, Vincent Pierre Lamirand, Axel Guy Marie Laureau, Dimitri Rochman

The Bayesian Monte Carlo technics requires individual evaluations of random cross section files based on a Total Monte Carlo propagation. This article discusses the use of a Correlated Sampling acceleration applied to TMC calculations for experiments where ...

EPJ Web of conference2018

Convergence Analysis and Criterion for Data Assimilation with Sensitivities from Monte Carlo Neutron Transport Codes

Andreas Pautz, Daniel Jerôme Siefman, Mathieu Hursin

Sensitivity coefficients calculated with Monte Carlo neutron transport codes are subject to statistical fluctuations. The fluctuations affect parameters that are calculated with the sensitivity coefficients. The convergence study presented here describes t ...

ANS2018

Statistical Burnup Distribution Of Moving Pebbles In Htr-Pm Reactor

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

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

AMER SOC MECHANICAL ENGINEERS2018

A Simplified Numerical Benchmark For Pool-Type Sodium Fast Reactors

Konstantin Mikityuk, Andreas Pautz, Stefan Radman, Carlo Fiorina

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

Design of Separated Element Reflector Experiments in CROCUS: PETALE

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

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

Case Study of Data Assimilation Methods with the LWR-Proteus Phase II Experimental Campaign

Andreas Pautz, Daniel Jerôme Siefman, Mathieu Hursin

This paper describes the application of data assimilation methods to CASMO-5 simulations of a Proteus research reactor experiment. Its focus is a comparison and evaluation of three prominent data assimilation methods: generalized linear least squares, MOCA ...

2017

Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes

Andreas Pautz, Daniel Jerôme Siefman, Adolfo Rais, Mathieu Hursin

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 ...

2017

Design of Separated Element Reflector Experiments in CROCUS: PETALE

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

The present article describes the preliminary design studies for an oncoming experimental programme at the CROCUS facility. CROCUS is a teaching and research zero-power reactor operated by the Laboratory for Reactor Physics and Systems Behaviour (LRS) at t ...

2017

Future experimental programmes in the CROCUS reactor

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

CROCUS is a teaching and research zero-power reactor operated by the Laboratory for Reactor Physics and Systems Behaviour (LRS) at the Swiss Federal Institute of Technology (EPFL). Three new experimental programmes are scheduled for the forthcoming years. ...

2016

Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor

Gaëtan Girardin, Andreas Pautz, Daniel Jerôme Siefman, Adolfo Rais, Mathieu Hursin

This paper summarizes the results of modeling methodologies developed for the zero-power (100 W) teaching and research reactor CROCUS located in the Laboratory for Reactor Physics and Systems Behavior (LRS) at the Swiss Federal Institute of Technology in L ...

2015

Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL

Gaëtan Girardin, Andreas Pautz, Daniel Jerôme Siefman, Adolfo Rais, Mathieu Hursin

In order to analyze the steady state and transient behavior of the CROCUS reactor, several methods and models need to be developed in the areas of reactor physics, thermal-hydraulics, and multiphysics coupling. The long-term objectives of this project are ...

2015

A Methodology for Global Sensitivity Analysis for Time-Dependent Code Output Applied to Reflood Simulation in TRACE

Damar Canggih Wicaksono, Andreas Pautz, Omar Zerkak

Understanding properly the impact of model parameters and their interactions on the predictions is required for an appropriate model assessment. For simulation of reflooding following a LOCA, this requirement is justified because the important parameters a ...

2015

Sensitivity Analysis of a Bottom Reflood Simulation using Morris Screening Method

Damar Canggih Wicaksono, Andreas Pautz, Omar Zerkak

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 ...

2014

Study of Nuclear Decay Data Contribution to Uncertainties in Heat Load Estimations for Spent Fuel Pools

Hakim Ferroukhi, Andreas Pautz, Alexander Vasiliev, Mathieu Hursin

At the Paul Scherrer Institut (PSI), a methodology for nuclear data uncertainty propagation in CASMO-5M (C5M) assembly calculations is under development. This paper presents a preliminary application of this methodology to C5M decay heat calculations. Appl ...

Academic Press Inc Elsevier Science2014

Exploring Variability in Reflood Simulation Results: an Application of Functional Data Analysis

Damar Canggih Wicaksono, Andreas Pautz, Omar Zerkak

In this paper we followed the functional data analysis (FDA) paradigm to summarize the output of computer code simulating a reflood transient. The paradigm stands on the assumption that the data (code output) is generated by a smooth, albeit complex, proce ...

2014

Comparison of Two Approaches for Nuclear Data Uncertainty Propagation in MCNPX for Selected Fast Spectrum Critical Benchmarks

Tiankai Zhu, Hakim Ferroukhi, Andreas Pautz, Alexander Vasiliev, Dimitri Rochman

Nuclear data uncertainty propagation based on stochastic sampling ( SS) is becoming more attractive while leveraging modern computer power. Two variants of the SS approach are compared in this paper. The Total Monte Carlo (TMC) method by the Nuclear Resear ...

Academic Press Inc Elsevier Science2014

Verification of a reactor physics calculation scheme for the CROCUS reactor

Gaëtan Girardin, Andreas Pautz, Daniel Jerôme Siefman, Adolfo Rais, Mathieu Hursin

CROCUS is a zero power (100 W) reactor of the Laboratory for Reactor Physics and Systems Behavior (LRS) at the Swiss Federal Institute of Technology, Lausanne (EPFL). It is used for teaching and research purposes. Its modeling has relied so far on diffusio ...

2014

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