Publication

A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions

Related publications (34)

Advanced methodologies for modeling and assessment of SFR safety functions

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

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

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

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

ASME2020

Parametric sensitivity in the Sabatier reaction over Ru/Al2O3 - theoretical determination of the minimal requirements for reactor activation

Andreas Züttel, Noris André Gallandat, Emanuele Moioli

The methanation of carbon dioxide is an option for chemical storage of renewable energy together with greenhouse gas reutilization because it offers a product with a high energy density. The reaction CO2 + 4H(2) CH4 + 2H(2)O is performed on a Ru/Al2O3 cata ...

ROYAL SOC CHEMISTRY2019

A coarse-mesh methodology for modelling of single-phase thermal-hydraulics of ESFR innovative assembly design

Andreas Pautz, Konstantin Mikityuk, Carlo Fiorina, Stefan Radman

The GeN-Foam multi-physics code enables coupled thermal-hydraulic, neutronic, and thermal-mechanical analysis of fast reactor cores with 3-D unstructured deformable meshes. Advances within the Horizon2020 ESFR-SMART project, as well as trends towards highe ...

ELSEVIER SCIENCE SA2019

Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

Minh Quang Tran

The findings of the EU 'Materials Assessment Group' (MAG), within the 2012 EU Fusion Roadmap exercise, are discussed. MAG analysed the technological readiness of structural, plasma facing and high heat flux materials for a DEMO concept to be constructed in ...

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, Jiri Krepel, Kaichao Sun

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

Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics

Kaichao Sun

In order to meet the steadily increasing worldwide energy demand, nuclear power is expected to continue playing a key role in electricity production. Currently, the large majority of nuclear power plants are operated with thermal-neutron spectra and need r ...

EPFL2012

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

Analysis of selected Phenix EOL tests with the FAST code system - Part I: Control-rod-shift experiments

Rakesh Chawla, Konstantin Mikityuk, Aurélia Chenu

The end-of-life (EOL) tests recently performed at the Phenix reactor present a unique opportunity to validate computational tools used for Sodium-cooled Fast Reactor (SFR) static and transient analysis. In the first part of the current study, PSI's FAST co ...

Elsevier2012

The generation IV gas-cooled fast reactor

Manuel Alexandre Pouchon, Konstantin Mikityuk

The gas cooled fast reactor (GFR) is a helium-cooled fast spectrum reactor operating within a closed fuel cycle. It combines the advantages of fast reactors, in terms of a more sustainable use of uranium resources and waste minimisation, with the wider app ...

Societe Francaise d'Energie Nucleaire2011

Graph Chatbot

Chat with Graph Search

Ask any question about EPFL courses, lectures, exercises, research, news, etc. or try the example questions below.

DISCLAIMER: The Graph Chatbot is not programmed to provide explicit or categorical answers to your questions. Rather, it transforms your questions into API requests that are distributed across the various IT services officially administered by EPFL. Its purpose is solely to collect and recommend relevant references to content that you can explore to help you answer your questions.