TY - GEN
T1 - Experiment on the compatibility of single and bimetallic alloys in a subscale flowing flibe loop
AU - Weitzel, David
AU - Lee, Youho
AU - Short, Michael
AU - Laufer, Mike
AU - Sham, Sam
N1 - Publisher Copyright:
© 2018 American Nuclear Society. All rights reserved.
PY - 2018
Y1 - 2018
N2 - Much progress has recently been made on Molten Salt Reactor (MSR) technology with the strategic support of the Department of Energy (DOE). However, concerns regarding the structural material's compatibility with the salt have hampered the detailed design and evaluation of reliability and economics. Existing research also neglects fluid flow when measuring alloy dissolution. FLiBe flow affects species diffusion through the salt and in turn modifies the reaction kinetics at the alloy surface. Without a proper understanding of the flow effects on alloy dissolution, MSR performance assessments will inevitably remain imprecise. This research entails the construction of a subscale molten salt loop to test the effects of FLiBe flow on the corrosion rate of various alloys. Our test loop will consist of a molten salt pump connected to a bimetallic composite test loop with a sample holder for the tested alloys. The salt temperature and velocity can be varied independently to replicate the varied operating conditions in the MSR and better characterize the effects of FLiBe flow on corrosion. Investigating the effects of salt flow on alloy element dissolution will advance material choice for key reactor components. These findings will enable nuclear engineers to create more detailed and accurate plant designs.
AB - Much progress has recently been made on Molten Salt Reactor (MSR) technology with the strategic support of the Department of Energy (DOE). However, concerns regarding the structural material's compatibility with the salt have hampered the detailed design and evaluation of reliability and economics. Existing research also neglects fluid flow when measuring alloy dissolution. FLiBe flow affects species diffusion through the salt and in turn modifies the reaction kinetics at the alloy surface. Without a proper understanding of the flow effects on alloy dissolution, MSR performance assessments will inevitably remain imprecise. This research entails the construction of a subscale molten salt loop to test the effects of FLiBe flow on the corrosion rate of various alloys. Our test loop will consist of a molten salt pump connected to a bimetallic composite test loop with a sample holder for the tested alloys. The salt temperature and velocity can be varied independently to replicate the varied operating conditions in the MSR and better characterize the effects of FLiBe flow on corrosion. Investigating the effects of salt flow on alloy element dissolution will advance material choice for key reactor components. These findings will enable nuclear engineers to create more detailed and accurate plant designs.
UR - http://www.scopus.com/inward/record.url?scp=85050136241&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:85050136241
T3 - Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
SP - 1176
EP - 1182
BT - Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
PB - American Nuclear Society
T2 - 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
Y2 - 8 April 2018 through 11 April 2018
ER -