Neutronics and fuel cycle modeling of a thorium-fueled two-fluid molten salt iso-breeder reactor
Authors:
- C. Erika MossCMC. Erika Moss
- Ondřej ChválaOCOndřej Chvála
- Harrison ReisingerHRHarrison Reisinger
- Alexander M. WheelerAWAlexander M. Wheeler
- Dallas MoserDMDallas Moser
- 8 July 2022
- journal article
- research article
- Published by Elsevier in Annals of Nuclear Energy
- Vol. 177
Abstract
No abstract availableKeywords
This publication has 30 references indexed in Scilit:
- The molten salt reactor (MSR) in generation IV: Overview and perspectivesProgress in Nuclear Energy, 2014
- Development of an OpenFOAM model for the Molten Salt Fast Reactor transient analysisChemical Engineering Science, 2014
- An extended version of the SERPENT-2 code to investigate fuel burn-up and core material evolution of the Molten Salt Fast ReactorJournal of Nuclear Materials, 2013
- Safety assessment of molten salt reactors in comparison with light water reactorsJournal of Radiation Research and Applied Sciences, 2013
- Investigation of the MSFR core physics and fuel cycle characteristicsProgress in Nuclear Energy, 2013
- An approach to the MSR dynamics and stability analysisProgress in Nuclear Energy, 2013
- The influence of lower plenum and distribution plates to thermal hydraulics characteristics of MSRNuclear Engineering and Design, 2013
- Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedureAnnals of Nuclear Energy, 2013
- Potential of thorium molten salt reactorsdetailed calculations and concept evolution with a view to large scale energy productionProgress in Nuclear Energy, 2005
- A Review on Boron CarbideKey Engineering Materials, 1991