European outlook for LMFR thermal hydraulics

F. Roelofs, A. Shams, J. Pacio, V. Moreau, P. Planquart, K. Van Tichelen, I. Di Piazza, M. Tarantino

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

11 Scopus citations

Abstract

Liquid metal cooled reactors are envisaged to play an important role in the future of nuclear energy production because of their possibility to use natural resources efficiently and to reduce the volume and lifetime of nuclear waste. Typically, sodium and lead(-alloys) are envisaged as coolants for such reactors. Obviously, in the development of these reactors, thermal-hydraulics is recognized as a key (safety) challenge. This paper will present recent developments and initiatives with respect to liquid metal cooled reactor thermal-hydraulics. The initiatives to be discussed encompass liquid metal heat transfer, fuel assembly thermal-hydraulics, pool thermal-hydraulics, and system thermal-hydraulics. With respect to liquid metal heat transfer, the purpose is to start from the most promising routes and develop and validate a model which can simultaneously deal with different flow regimes (natural, mixed, and forced convection). Considering fuel assemblies, the aim will be to take the next steps in liquid metal fast reactor fuel assembly modelling, mainly focusing on validation and evaluation of accidental conditions. With respect to pool thermal-hydraulics, the purpose will be to develop and validate sufficiently accurate methods to model the coolant behavior in a liquid metal reactor pool. When considering the system scale, similarly, the purpose will be to validate and improve system thermal-hydraulics models, but also to further develop and validate multi-scale approaches.

Original languageEnglish
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages7414-7425
Number of pages12
ISBN (Electronic)9781510811843
StatePublished - 2015
Externally publishedYes
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: 30 Aug 20154 Sep 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume9

Conference

Conference16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/TerritoryUnited States
CityChicago
Period30/08/154/09/15

Keywords

  • Fast reactor
  • Liquid metal
  • Thermal-hydraulics

ASJC Scopus subject areas

  • Instrumentation
  • Nuclear Energy and Engineering

Fingerprint

Dive into the research topics of 'European outlook for LMFR thermal hydraulics'. Together they form a unique fingerprint.

Cite this