TY - JOUR
T1 - The corrosion effects of neutron activation of 2LiF-BeF2 (FLiBe)
AU - Vergari, Lorenzo
AU - Scarlat, Raluca O.
AU - Hayes, Ryan D.
AU - Fratoni, Massimiliano
N1 - Funding Information:
This research is being performed using funding received from the DOE Office of Nuclear Energy’s Nuclear Energy University Program, project IRP-20-22026. This work was supported in part by FUTURE (Fundamental Understanding of Transport Under Reactor Extremes), an Energy Frontier Research Center funded by the US Department of Energy, Office of Science, Basic Energy Sciences. This research used the Savio computational cluster resource provided by the Berkeley Research Computing program at the University of California, Berkeley (supported by the UC Berkeley Chancellor, Vice Chancellor for Research, and Chief Information Officer). Lorenzo Vergari acknowledges the Berkeley Graduate Fellowship.
Publisher Copyright:
© 2022
PY - 2023/3
Y1 - 2023/3
N2 - The redox effect of activation reactions in molten salts has been previously qualitatively defined but never quantified. Here, we quantify the corrosion effects of neutron activation of FLiBe. Rates of change of activation products are computed for FHR and ARC. The impact of activation reactions on salt chemistry is quantitatively compared to other environmental effects of similar consequences on the salt. The results are applied to a redox control case-study and an irradiation-corrosion experiment. The results are presented in a manner useful to the reactor chemist and designer concerned with corrosion and chemistry control and tritium management in irradiated FLiBe, and design of salt-irradiation experiments.
AB - The redox effect of activation reactions in molten salts has been previously qualitatively defined but never quantified. Here, we quantify the corrosion effects of neutron activation of FLiBe. Rates of change of activation products are computed for FHR and ARC. The impact of activation reactions on salt chemistry is quantitatively compared to other environmental effects of similar consequences on the salt. The results are applied to a redox control case-study and an irradiation-corrosion experiment. The results are presented in a manner useful to the reactor chemist and designer concerned with corrosion and chemistry control and tritium management in irradiated FLiBe, and design of salt-irradiation experiments.
KW - FLiBe fusion blanket
KW - fluoride-salt cooled high-temperature reactor (FHR)
KW - Irradiation-corrosion in molten salts
KW - Neutron-activation driven corrosion
KW - Redox control in molten salts
KW - Tritium production
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U2 - 10.1016/j.nme.2022.101289
DO - 10.1016/j.nme.2022.101289
M3 - Article
AN - SCOPUS:85145252285
SN - 2352-1791
VL - 34
JO - Nuclear Materials and Energy
JF - Nuclear Materials and Energy
M1 - 101289
ER -