Publications associées à Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code

Atomic level insight into irradiation effects in nuclear fuel materials

Microstructural evolution during in-pile irradiation, radiation damage effects and fission products behavior in UO2 nuclear fuel are key issues in understanding and for the modeling of the performance as well as safety characteristics of nuclear fuels in t ...

EPFL2024

Innovative thermophysical characterization of an ATF composite cladding: the case of silicon carbide

Andrea Cavaliere

Nuclear power is a powerful technology that plays an important role in the fight against climate change, and research is continuously engaged in studies that could further improve its safety. After the Fukushima accident, Accident Tolerant Fuels research h ...

EPFL2024

Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments

Andreas Pautz, Alessandro Scolaro, Carlo Fiorina, 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 SA2023

Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5

Stefano Caruso, Andreas Pautz, Dimitri Rochman

Decay heat calculations of spent nuclear fuel (SNF) using Polaris and ORIGEN codes in the SCALE code sys-tem, and CASMO5 code, are validated using measurements from the Clab and GE-Morris facilities. Multiple hypothesis testing, relying on permutations and ...

PERGAMON-ELSEVIER SCIENCE LTD2022

Operational Map And Thermal Performance Of A Thermosyphon Cooling System For Compact Servers

John Richard Thome, Jackson Braz Marcinichen, Raffaele Luca Amalfi, Filippo Cataldo

This paper advances the state-of-the-art in novel passive two-phase systems for more efficient cooling of datacenters and telecom central offices compared to the traditional air-based cooling solutions (e.g. aisle-based containment systems). The proposed p ...

AMER SOC MECHANICAL ENGINEERS2021

Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules

Stefano Caruso, Andreas Pautz, Dimitri Rochman

Decay heat residuals of spent nuclear fuel (SNF), i.e., the differences between calculations and measurements, were obtained previously for various spent fuel assemblies (SFA) using the Polaris module of the SCALE code system. In this paper, we compare dec ...

2021

Investigation of the density shoulder formation by using self-consistent simulations of plasma turbulence and neutral kinetic dynamics

Paolo Ricci, Nicola Vianello, Maurizio Giacomin, Davide Mancini

Simulations of plasma turbulence in a lower single-null magnetic configurations are presented. The plasma dynamics is modelled by the drift-reduced two-fluid Braginskii equations that are coupled with a kinetic model for a single neutral species that consi ...

IOP Publishing Ltd2021

Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm

Hakim Ferroukhi, Andreas Pautz, Alexander Vasiliev, Dimitri Rochman

This paper presents an approach for the optimisation of geological disposal canister loadings, combining high resolution simulations of used nuclear fuel characteristics with an articial neural network and a genetic algorithm. The used nuclear fuels (produ ...

SPRINGER LONDON LTD2021

Thermal management of components for high energy physics experiments and space applications

Timothée Robert Sophus Frei

High-energy physics (HEP) experiments and space missions share a common challenge: thermal management in harsh environments. The severe constraints in both fields make cooling of electronic components a major design concern. This thesis aims to develop hig ...

EPFL2021

Development of a Novel Finite Volume Methodology for Multi-Dimensional Fuel Performance Applications

Alessandro Scolaro

Fuel performance codes are an essential tool for ensuring the safe and economic opera-tion of nuclear reactors. Traditionally, these codes have been developed following a simple 1.5-D modelling approach, where the fuel behavior is simplified by assuming ax ...

EPFL2021

Simulation and experimental validation of pulsating heat pipes

John Richard Thome, Jackson Braz Marcinichen, Filippo Cataldo, Philippe Aubin

The one-dimensional transient numerical code of JJ Cooling Innovation has been significantly improved to simulate the thermal/hydraulic performance of pulsating heat pipes (PHPs). Using a mechanistic approach, the liquid slug and vapor plug flows and their ...

PERGAMON-ELSEVIER SCIENCE LTD2021

A Coarse-mesh Methodology for the Analysis of One and Two-phase Nuclear Reactor Thermal-hydraulics in a Multi-physics Context

Stefan Radman

The analysis of nuclear reactors for performance and safety assessment benefits from the use of computational tools. In this context, this work aims at the development and application of a thermal-hydraulics methodology and related software that respond to ...

EPFL2021

Performance of lightweight and heavyweight building walls with naturally ventilated passive and active facades

Mohammad Rahiminejad, Dolaana Khovalyg

Well-designed ventilated air-spaces behind external claddings in the building envelope can potentially reduce thermal energy flow in the entire wall structure. In this study, the impact of the dynamic thermo-hydraulic behavior of the flow in the naturally ...

2021

Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters

Hakim Ferroukhi, Andreas Pautz, Alexander Vasiliev, Dimitri Rochman

In this study, an optimization of the canister loading for used nuclear fuels is performed, solely based on their decay heat values. By taking into account the individual irradiation history for each fuel assembly, as well as with a number of assumptions o ...

ELSEVIER SCIENCE SA2020

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

Gaëtan Girardin, Abdelhamid Dokhane, Hakim Ferroukhi, Andreas Pautz, Dionysios Chionis

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 ...

PERGAMON-ELSEVIER SCIENCE LTD2020

Systematic Sensitivity and Uncertainty Analysis of Sodium-Cooled Fast Reactor Systems

Friederike Bostelmann

Sodium-cooled fast reactor (SFR) technologies have the potential to guarantee energy supply and to reduce the burden of nuclear waste for future generations. For an adequate simulation of these reactor systems, well-established tools that have so far been ...

EPFL2020

The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator

Daniel Godat, Pavel Frajtag, Andreas Pautz, Adolfo Rais, Oskari Ville Pakari, Vincent Pierre Lamirand, Mathieu Hursin, Carlo Fiorina, Axel Guy Marie Laureau

The present article presents the mechanical characterization of the fuel rods oscillator developed for the purposes of the COLIBRI experimental program in CROCUS. COLIBRI aims at investigating the radiation noise related to fuel vibrations. The main motiva ...

2020

Modelling of fuel fragmentation, relocation and dispersal during Loss-of-Coolant Accident in Light Water Reactor

Vladimir Vladimirov Brankov

Recent LOCA tests with high burnup fuel at the OECD Halden Reactor Project and at Studsvik demonstrated the susceptibility of the fuel to fragment to small pieces, to relocate and possibly cause a hot-spot effect and to be dispersed in the event of claddin ...

EPFL2017

Investigation of the thermal conductivity of SiC/SiC cladding before and after irradiation

Loïc Guillaume Fave

Silicon carbide based composites are candidates for structural components and fuel claddings in nuclear power plants. In the frame of accident tolerant fuel research, the effective through-thickness thermal conductivity of SiC/SiC prototype claddings is in ...

EPFL2017

Overview of ASDEX Upgrade results

Basil Duval, Timothy Goodman, Olivier Sauter, Stefano Coda, Alberto Bottino, Marco Wischmeier, Andrea Scarabosio, Hartmut Zohm, Laurie Porte, Yann Camenen, Thomas Binderup Jensen, Emiliano Fable, Federico Alberto Alfredo Felici, Dávid Wágner, Doohyun Kim, Antoine Pierre Emmanuel Alexis Merle, Emanuele Poli, Nicola Vianello, Giovanni Tardini, Donghyun Kim, Cristian Sommariva, Otto Asunta, Haomin Sun, Xiao Wang, Gergely Papp, Bernhard Sieglin

The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and the preparation of ITER operation, as well as addressing physics issues for a future DEMO design. Since 2015, AUG is equipped with a new pair of ...

IOP Publishing Ltd2017