Concept

Passive nuclear safety

Publications associées (28)

Status of the ITER Electron Cyclotron Heating and Current Drive System

The electron cyclotron (EC) heating and current drive (H&CD) system developed for the ITER is made of 12 sets of high-voltage power supplies feeding 24 gyrotrons connected through 24 transmission lines (TL), to five launchers, four located in upper ports a ...

Springer2016

Progress in the ITER electron cyclotron heating and current drive system design

Timothy Goodman

An electron cyclotron system is one of the four auxiliary plasma heating systems to be installed on the ITER tokamak. The ITER EC system consists of 24 gyrotrons with associated 12 high voltage power supplies, a set of evacuated transmission lines and two ...

Elsevier Science Sa2015

Large eddy simulation of particulate flow inside a differentially heated cavity

Michel Deville, Emmanuel Leriche, Christoph Bosshard

In nuclear safety, some severe accident scenarios lead to the presence of fission products in aerosol form in the closed containment atmosphere. It is important to understand the particle depletion process to estimate the risk of a release of radioactivity ...

Elsevier2014

Shot-clay MX-80 bentonite: an assessment of the hydro-mechanical behaviour

Lyesse Laloui, Alessio Ferrari, Ali Seiphoori

This study presents the results of an experimental study conducted to characterise the hydro-mechanical behaviour of shot-clay MX-80 bentonite. In the shot-clay process, granular bentonite was mixed continuously with water and shot on the walls of a tunnel ...

Elsevier2014

Coupled 3-D Neutronics/Thermal-Hydraulics Optimization Study For Improving The Response Of A 3600 Mw(Thermal) Sfr Core To An Unprotected Loss-Of-Flow Accident

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

The sodium-cooled fast reactor (SFR), as a fast neutron spectrum system, is characterized by several performance advantages. In particular, the long-term operation of an SFR core in a closed fuel cycle will lead to an equilibrium state, where both reactivi ...

Amer Nuclear Soc2013

Application of Power Time-Projection on the Operator Splitting Coupling Scheme of the TRACE/S3K Coupled Code

Rakesh Chawla, Damar Canggih Wicaksono, Hakim Ferroukhi

This paper reports refinement studies on the temporal coupling scheme and time-stepping management of TRACE/S3K, a dynamically coupled code version of the thermal-hydraulics system code TRACE and the 3D core simulator Simulate-3K. The studies were carried ...

American Nuclear Society2013

A novel design approach for a neutron measurement station for burnt fuel

Rakesh Chawla, Mathieu Hursin

The design and characterization of a passive neutron measurement station for highly burnt fuel has been undertaken at the Paul Scherrer Institute (PSI). The measurement station aims at the determination of the total neutron emission rate of full-length lig ...

Elsevier2012

Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

Experimental results from the unprotected phase of the Natural Convection (NC) Test performed in the Phenix reactor in the frame of end-of-life (EOL) experiments have been used to qualify the FAST code system for Sodium-cooled Fast Reactor (SFR) transient ...

Elsevier2012