Molten
salts have favorable material properties for use in high-temperature
energy systems, including thermal energy storage systems, concentrating
solar power plants, nuclear reactors, and various industrial manufacturing
processes. Knowledge of chemical and thermophysical property data
is essential for the design and optimization of these systems, yet
data are often limited or uncertain for many candidate salts due to
the difficulty of thermophysical property measurements at relevant
temperatures (e.g., 500–900 °C). Here, the density of
molten LiF-NaF-KF eutectic is reassessed through review of previous
experimental data, new density measurements from 470 to 800 °C,
and semiempirical modeling. The density was measured using the displacement
technique. Compositional and temperature-dependent density estimates
were calculated with a multidimensional Redlich–Kister model.
The results of the new experimental measurements agree within 2% of
the modeled density of molten eutectic LiF-NaF-KF. The Redlich–Kister
model’s prediction shows a near-ideal density behavior for
the LiF-NaF-KF system and is promising for the estimation of off-eutectic
LiF-NaK-KF densities. Finally, through review of the existing literature
and comparison to new measurements, recommendations are made for the
density of LiF-NaF-KF.
Liquid Sn is one of the promising coolants for liquid surface divertor concept of fusion reactors. However, the compatibility between liquid Sn and structural materials is an important issue that has to be addressed, because liquid Sn is extremely corrosive to steels at high temperatures. The corrosion may be mitigated when a protective Al 2 O 3 layer is formed on the surface of alumina forming steels. However, the effect of neutron irradiation on the integrity of protective layer is not made clear so far. Japan and US joint research project "FRONTIER" started in 2019 to investigate the material compatibility under neutron irradiation. The purpose of the present study is to develop the conceptual design of the irradiation test capsule which enables material compatibility tests for the alumina forming steels -liquid metal systems under neutron irradiation in the High Flux Isotope Reactor at Oak Ridge National Laboratory, TN, USA. The three dimensional drawing of capsule structure was then developed. The validity of the material selections for the capsule design was investigated by means of corrosion tests of SiC, Si 3 N 4 , Ti, and Mo in liquid Sn at 773 K for 262 hr.
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