Publications related to Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model

Neutron-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 Inc2024

Advanced methodologies for modeling and assessment of SFR safety functions

Janos Bodi

The present doctoral work was performed to contribute to the conceptual design development and safety assessment of a Generation IV Sodium Fast Reactor (SFR) in the frame of the European Sodium Fast Reactor Safety Measures Assessment and Research Tools (ES ...

EPFL2022

A Hybrid Approach to Neutron Transport with Thermal-hydraulic Feedback for Reactor Transient Analysis

Alexander Aures

Understanding the time-dependent behaviour of a nuclear reactor following an intended or unintended change of the reactor conditions is of crucial importance to the safe operation of nuclear reactors. Safety evaluations of nuclear reactors involve the anal ...

EPFL2021

Development of Advanced Methodologies for Monitoring and Modelling of Neutron Noise in Modern LWR Cores

Dionysios Chionis

Nuclear reactors are inherently stochastic systems, in which neutronic and thermal-hydraulic parameters fluctuate continuously even during steady-state conditions. In addition, structural components vibrate due to the coolant hydraulic forces. This stochas ...

EPFL2020

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

László Forró, Endre Horvath, Andrzej Sienkiewicz, Bálint Náfrádi, Márton Kollár, Pavao Roko Andricevic

Detection and direct power conversion of high energy and high intensity ionizing radiation could be a key element in next generation nuclear reactor safety systems and space-born devices. For example, the Fukushima catastrophe in 2011 could have been large ...

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

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

Design Concept and Thermal & x2013;Mechanical Analysis of the Optical Mirror (M3) for the ITER ECH Upper Launcher

Timothy Goodman, René Chavan

The mirror M3 is a part of the in-vessel quasi-optical beam propagation system for the ITER electron cyclotron heating upper launcher (ECHUL). The millimeter waves are guided through fixed mirror sets (M1, M2, and M3) and the front steering mirror set (M4) ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2020

Performance assessment of a 3-D steady-state and spatial kinetics model for the CROCUS reactor

Adolfo Rais

This dissertation covers both experimental and numerical neutronics studies to evaluate the adequacy of the Serpent/PARCS code sequence for modeling the steady-state and kinetics behavior of the CROCUS reactor. The reactor presents design characteristics t ...

EPFL2018

One-Dimensional Fluid-Structure Interaction Models in Pressurized Fluid-Filled Pipes: A Review

Anton Schleiss, Pedro Filipe De Almeida Manso

The present review paper aims at collecting and discussing the research work, numerical and experimental, carried out in the field of Fluid-Structure Interaction (FSI) in one-dimensional (1D) pressurized transient flow in the time-domain approach. Backgrou ...

MDPI2018

Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model

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Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators

Advanced methodologies for modeling and assessment of SFR safety functions

A Hybrid Approach to Neutron Transport with Thermal-hydraulic Feedback for Reactor Transient Analysis

Development of Advanced Methodologies for Monitoring and Modelling of Neutron Noise in Modern LWR Cores

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

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

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

Design Concept and Thermal & x2013;Mechanical Analysis of the Optical Mirror (M3) for the ITER ECH Upper Launcher

Performance assessment of a 3-D steady-state and spatial kinetics model for the CROCUS reactor

One-Dimensional Fluid-Structure Interaction Models in Pressurized Fluid-Filled Pipes: A Review

Advanced methodologies for modeling and assessment of SFR safety functions

A Hybrid Approach to Neutron Transport with Thermal-hydraulic Feedback for Reactor Transient Analysis

Development of Advanced Methodologies for Monitoring and Modelling of Neutron Noise in Modern LWR Cores

Radiation detection and energy conversion in nuclear reactor environments by hybrid photovoltaic perovskites

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

Design Concept and Thermal & x2013;Mechanical Analysis of the Optical Mirror (M3) for the ITER ECH Upper Launcher

Performance assessment of a 3-D steady-state and spatial kinetics model for the CROCUS reactor

Neutron-Gamma Noise Measurements in a Zero-Power Reactor Using Organic Scintillators

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

One-Dimensional Fluid-Structure Interaction Models in Pressurized Fluid-Filled Pipes: A Review