Advanced liquid fuel molten salt reactor core simulation using gen-foam

  • Muhammad Altahhan
  • , Sandesh Bhaskar
  • , Paolo Balestra
  • , Jason Hou
  • , Maria Avramova
  • , Nicholas Smith

Research output: Contribution to conferencePaperpeer-review

2 Scopus citations

Abstract

In this study, a hybrid two-dimensional (2D) / three-dimensional (3D) Liquid Fuel Molten Salt Reactor (LFMSR) core is modelled using the Multi-physics C++ code GeN-Foam (General Nuclear Foam). GeN-Foam has three main sub-solvers - for neutron kinetics, thermal hydraulics, and thermal mechanics. A steady state analysis of a simplified 2D LFMSR model has been performed assuming rotational symmetry to cross validate the code with the commercial ANSYS Computational Fluid Dynamics (CFD) code Fluent. The calculations showed a very good agreement between the two codes allowing moving onto a 3D model simulation. A coupled 3D neutron kinetic and CFD steady state analysis of the 3D LFMSR core has been performed modeling one quarter of the core using the core symmetry to reduce the computational time. The GeN-Foam neutron kinetics sub-solver has been designed to consider also the drifting of the delayed neutrons precursors in LFMSR, a capability not yet implemented in the most of current neutron kinetics codes. The mixed Uranium and Plutonium chloride fuel has been selected in this preliminary study. The calculation results meet the expectations showing that GeN-Foam has all the features necessary for LFMSR design modeling and simulation. The delayed neutrons precursors behavior is as expected - the longer-lived isotopes accumulate near the outlet while the short-lived ones lay at the generation location. The calculated maximum temperature is close to the expected one and the velocity profile is consistent with a low viscosity, high density fluid velocity profile.

Original languageEnglish
Pages1248-1256
Number of pages9
StatePublished - 2018
Externally publishedYes
EventInternational Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting - Orlando, United States
Duration: Nov 11 2018Nov 15 2018

Conference

ConferenceInternational Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018 - Held in conjunction with the 2018 American Nuclear Society (ANS) Winter Meeting
Country/TerritoryUnited States
CityOrlando
Period11/11/1811/15/18

Keywords

  • CFD
  • GeN-Foam
  • LFMSR
  • Multi-physics

Fingerprint

Dive into the research topics of 'Advanced liquid fuel molten salt reactor core simulation using gen-foam'. Together they form a unique fingerprint.

Cite this