Coupled Thermal-Hydraulic Analysis and Species Mass Transport in a Versatile Experimental Salt Irradiation Loop (VESIL) Using CTF

With the resurgence of interest in molten salt reactors, there is a need for new experiments and modeling capabilities to characterize the unique phenomena present in this fluid fuel system. A Versatile Experimental Salt Irradiation Loop (VESIL) is currently under investigation at Idaho National Lab...

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Main Authors: Samuel A. Walker, Abdalla Abou-Jaoude, Zack Taylor, Robert K. Salko, Wei Ji
Format: Article
Language:English
Published: MDPI AG 2021-08-01
Series:Journal of Nuclear Engineering
Subjects:
Online Access:https://www.mdpi.com/2673-4362/2/3/25
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author Samuel A. Walker
Abdalla Abou-Jaoude
Zack Taylor
Robert K. Salko
Wei Ji
author_facet Samuel A. Walker
Abdalla Abou-Jaoude
Zack Taylor
Robert K. Salko
Wei Ji
author_sort Samuel A. Walker
collection DOAJ
description With the resurgence of interest in molten salt reactors, there is a need for new experiments and modeling capabilities to characterize the unique phenomena present in this fluid fuel system. A Versatile Experimental Salt Irradiation Loop (VESIL) is currently under investigation at Idaho National Laboratory to be placed in the Advanced Test Reactor (ATR). One of the key phenomena this proposed experiment plans to elucidate is fission product speciation in the fuel-salt and the subsequent effects this has on the fuel-salt properties, source term generation, and corrosion control. Specifically, noble gases (Xe & Kr) will bubble out to a plenum or off-gas system, and noble metals (Mo, Tc, Te, etc.) will precipitate and deposit in specific zones in the loop. This work extends the mass transfer and species interaction models in CTF (Coolant-Boiling in Rod Arrays—Two Fluids) and applies these models to give a preliminary estimation of fission product behavior in the proposed VESIL design. A noble metal–helium bubble mass transfer model is coupled with the thermal-hydraulic results from CTF to determine the effectiveness of this insoluble fission product (IFP) extraction method for VESIL. Amounts of IFP species extracted to the off-gas system and species distributions in VESIL after a 60-day ATR cycle are reported.
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spelling doaj.art-66fe910520544701910d974bbed112e72023-11-22T13:47:15ZengMDPI AGJournal of Nuclear Engineering2673-43622021-08-012330931710.3390/jne2030025Coupled Thermal-Hydraulic Analysis and Species Mass Transport in a Versatile Experimental Salt Irradiation Loop (VESIL) Using CTFSamuel A. Walker0Abdalla Abou-Jaoude1Zack Taylor2Robert K. Salko3Wei Ji4Department of Mechanical, Aerospace, and Nuclear Engineering, Rensselaer Polytechnic Institute, 110 8th St, Troy, NY 12180, USAIdaho National Laboratory, 1955 N Fremont Ave, Idaho Falls, ID 83415, USAOak Ridge National Laboratory, 5200, 1 Bethel Valley Rd, Oak Ridge, TN 37830, USAOak Ridge National Laboratory, 5200, 1 Bethel Valley Rd, Oak Ridge, TN 37830, USADepartment of Mechanical, Aerospace, and Nuclear Engineering, Rensselaer Polytechnic Institute, 110 8th St, Troy, NY 12180, USAWith the resurgence of interest in molten salt reactors, there is a need for new experiments and modeling capabilities to characterize the unique phenomena present in this fluid fuel system. A Versatile Experimental Salt Irradiation Loop (VESIL) is currently under investigation at Idaho National Laboratory to be placed in the Advanced Test Reactor (ATR). One of the key phenomena this proposed experiment plans to elucidate is fission product speciation in the fuel-salt and the subsequent effects this has on the fuel-salt properties, source term generation, and corrosion control. Specifically, noble gases (Xe & Kr) will bubble out to a plenum or off-gas system, and noble metals (Mo, Tc, Te, etc.) will precipitate and deposit in specific zones in the loop. This work extends the mass transfer and species interaction models in CTF (Coolant-Boiling in Rod Arrays—Two Fluids) and applies these models to give a preliminary estimation of fission product behavior in the proposed VESIL design. A noble metal–helium bubble mass transfer model is coupled with the thermal-hydraulic results from CTF to determine the effectiveness of this insoluble fission product (IFP) extraction method for VESIL. Amounts of IFP species extracted to the off-gas system and species distributions in VESIL after a 60-day ATR cycle are reported.https://www.mdpi.com/2673-4362/2/3/25species transportmolten salt reactornoble metalnoble gashelium bubblingmass transfer
spellingShingle Samuel A. Walker
Abdalla Abou-Jaoude
Zack Taylor
Robert K. Salko
Wei Ji
Coupled Thermal-Hydraulic Analysis and Species Mass Transport in a Versatile Experimental Salt Irradiation Loop (VESIL) Using CTF
Journal of Nuclear Engineering
species transport
molten salt reactor
noble metal
noble gas
helium bubbling
mass transfer
title Coupled Thermal-Hydraulic Analysis and Species Mass Transport in a Versatile Experimental Salt Irradiation Loop (VESIL) Using CTF
title_full Coupled Thermal-Hydraulic Analysis and Species Mass Transport in a Versatile Experimental Salt Irradiation Loop (VESIL) Using CTF
title_fullStr Coupled Thermal-Hydraulic Analysis and Species Mass Transport in a Versatile Experimental Salt Irradiation Loop (VESIL) Using CTF
title_full_unstemmed Coupled Thermal-Hydraulic Analysis and Species Mass Transport in a Versatile Experimental Salt Irradiation Loop (VESIL) Using CTF
title_short Coupled Thermal-Hydraulic Analysis and Species Mass Transport in a Versatile Experimental Salt Irradiation Loop (VESIL) Using CTF
title_sort coupled thermal hydraulic analysis and species mass transport in a versatile experimental salt irradiation loop vesil using ctf
topic species transport
molten salt reactor
noble metal
noble gas
helium bubbling
mass transfer
url https://www.mdpi.com/2673-4362/2/3/25
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