Publications associées à Centrale nucléaire de Bruce

Dosimetry modeling and experimental validation for the PETALE program in the CROCUS reactor

Andreas Pautz, Vincent Pierre Lamirand, Pavel Frajtag, Axel Guy Marie Laureau

The PETALE experimental program in the CROCUS reactor intends to provide integral measurements on reactivity worth and dosimetry measurement to constrain nuclear data relative to stainless steel heavy reflectors. The experimental setup consists in eight su ...

2021

Design of Separated Element Reflector Experiments in CROCUS: PETALE

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

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

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

Design of Separated Element Reflector Experiments in CROCUS: PETALE

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

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

Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes

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

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

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

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

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

Heat Management for Process Intensification of Fast Exothermic Reactions in Microstructured Reactors

Julien Haber

Nowadays, the production in fine chemical and pharmaceutical industry is mostly carried out in large scale batch reactors having typically dimensions of a few meters to satisfy the demand of the market. Even though this technology has been widely used and ...

EPFL2013

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

Rakesh Chawla, Fabian Jatuff, Michaël Plaschy

The recent experimental programme conducted in the PROTEUS research reactor at the Paul Scherrer Institute (PSI) has concerned detailed investigations of advanced light water reactor (LWR) fuels. More than fifteen different configurations of the multi-zone ...

Elsevier Science Ltd.2009