High temperature corrosion studies in molten salt-FLiNaK

Sona, C.S.; Gajbhiye, Bhavesh D.; Hule, P. V.; Patwardhan, Ashwin W.; Mathpati, Channamallikarjun S.; Borgohain, A.; Maheshwari, N. K.

doi:10.1179/1743278213y.0000000135

Cited by 35 publications

(17 citation statements)

References 14 publications

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“…Lithium fluoride at room temperature and pressure is a simple and well-studied crystal with the rock salt structure [1][2][3]. It has found applications in optics, radiation detection, and nuclear reactors [4][5][6][7]. Herein, we study variations in the near-edge X-ray absorption fine structure (NEXAFS) [8] of this salt with temperature.…”

Section: Introductionmentioning

confidence: 99%

Temperature and radiation effects at the fluorine K-edge in LiF

Schwartz

Ponce

Friedrich

et al. 2017

Journal of Electron Spectroscopy and Related Phenomena

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The fluorine K-edge of LiF is studied both experimentally and theoretically as a function of temperature. Instantaneous thermal fluctuations in atomic positions are shown in molecular dynamics simulations to increase in amplitude from 0.029 to 0.064 nm in the temperature range from 40 to 298 K. This is sufficient to cause instantaneous deviations from local octahedral atomic symmetry in this rock-salt crystal, resulting in altered electronic structure. The lowered symmetry of the lowest core-excited states of fluorine atoms is evident in X-ray absorption spectra at the F K-edge. In addition, sufficient radiation exposure produces a new X-ray absorption peak, below the F K-edge of LiF, which is assigned to defects in LiF based on both calculations and comparison to previous experiments.

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Section: Introductionmentioning

confidence: 99%

Temperature and radiation effects at the fluorine K-edge in LiF

Schwartz

Ponce

Friedrich

et al. 2017

Journal of Electron Spectroscopy and Related Phenomena

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“…The tensile test and hardness test were conducted on the heated specimens, and the mechanical properties were compared. The SEM images were taken, and XRD analysis was done for performing the microstructural analysis [15][16][17].…”

Section: Introductionmentioning

confidence: 99%

Investigation on Hot Corrosion Behaviour of Inconel 625 and Incoloy 800H Superalloys with YSZ‐Thermal Barrier Coating Under High‐Temperature Environment for Bioreactor Applications

Hariharan

Anderson

Praveenkumar

et al. 2022

Journal of Nanomaterials

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Thermal energy storage is one of the promising technologies in the modern era for balancing the peak power demand without emitting much emission. Molten-salt technology plays a dominant role among the varieties of thermal energy storage systems. The difficulty in storing the molten-salt technology requires a storage material with high temperature, corrosion, and oxidation resistance properties. The nickel-based superalloys such as Inconel 625 and Incoloy 800H possess the desired properties to be used as a storage material for the molten salts. In this present work, the Incoloy 800H and Inconel 625 superalloy specimens were taken up for investigation. The specimens were coated with yttria-stabilized zirconia as a thermal barrier coating using a plasma spray process. The sodium chloride and potassium chloride molten salts with a weight fraction of 7 : 3 have been taken with both uncoated and YSZ-coated specimens, and specimens were heated up to 1000°C approximately. The specimens were heated for different hours such as 8, 12, and 16 hours, respectively. The increase in heating time also results in the increase in the tensile property of the specimens. The mechanical testing, such as tensile test and hardness test, was performed to comprehend the mechanical properties. Scanning electron microscope images and X-ray diffraction analysis were made to study the microstructural properties and the corrosion resistance property. From the test results, YSZ-coated specimens possess high corrosion resistance and high mechanical strength compared to the uncoated specimens.

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“…However, the challenge is extremely high corrosion with molten fluoride salts . From our previous work typical corrosion rates of high‐temperature alloys like Hastelloy‐B, Inconel‐625, and Hastelloy‐X in FLiNaK at 650°C are 3.02, 23.70, and 37.50 mm/year, respectively . Due to this, it is important to get the thermal hydraulics of the heat transfer medium at operating temperature with suitable material of construction.…”

Section: Introductionmentioning

confidence: 99%

“…As molten salts like FLiNaK and KCl‐MgCl 2 are highly corrosive in nature, high temperature (650°C‐850°C) corrosion studies have been carried out to investigate the materials compatible with various molten salts . FLiNaK being the most corrosive salt, the material of construction is selected accordingly after the corrosion studies.…”

Section: Introductionmentioning

confidence: 99%

“…Thus, based on the analysis from the literature review for the design of Generation‐IV nuclear reactors the major challenges were identified and experiments were planned accordingly. The material corrosion analysis in molten FLiNaK salt was carried out at high temperatures (650°C‐850°C) and the results are reported in our previous work . Based on the corrosion information, a high temperature forced convection loop for experimental thermal hydraulic studies of the extremely corrosive molten fluoride salts was designed and fabricated.…”

Section: Introductionmentioning

confidence: 99%

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Pretest in forced circulation molten salt heat transfer loop: Studies with thermia‐B

Gajbhiye

Sona

Mathpati

et al. 2019

Heat Trans. Asian Res.

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Molten salts have potential application as an efficient heat transfer medium in a primary and secondary heat exchanger in high temperature next-generation nuclear power plant. Thermal hydraulic studies are vital for reliable and cost-effective design of the nuclear power plant. Therefore heat transfer study of molten salts will play a vital role in this area. In this work, an experimental system was designed to study thermal hydraulics of the molten salt system up to 700°C. This work describes the pretest results of the experimental facility for extremely corrosive molten fluoride salts with a simulant thermia-B as the working fluid. In the present work, the details of the system are discussed and thermal-hydraulic data for heat transfer fluid thermia-B has been presented. Experiments were carried out at Reynolds number in the range of 4500 to 40 500 and Prandtl number in the range of 34 to 144.Effect of Reynolds number, melting tank temperature, and heat input to test section on forced convective heat transfer was studied under turbulent conditions. Comparison of the experimental data with different empirical correlations has been presented.Abbreviations: CFD, computational fluid dynamic; ICP-AES, inductively coupled plasma-atomic emission spectroscopy; LES, large eddy simulations; MFR, mass flow rates; NGNP, next-generation nuclear plant; PLC, programmable logic controller; RTD, resistance temperature detectors; SCADA, supervisory control and data acquisition; VFD, variable frequency drive; WTMM, wavelet transform modulus maxima. K E Y W O R D S molten salt heat transfer loop, Nusselt number, Reynolds number, thermic fluid, turbulent flow, wall heat flux 1 | INTRODUCTION Per capita, energy consumption relates directly to the overall development of any nation. As per the recent data (2016) per capita, the energy consumption of the United States is 1377 W, Russia is 854 W, France is 736 W, Australia is 1112 W, China is 510 W, and India is 128 W. Therefore, energy is an essential input for the sustained growth in development. The answer to this high and cost-effective energy requirement in future is nuclear power energy. Nuclear power is the cleanest form of mass-energy generation, producing no greenhouse gases like CO 2 , SO 2 , and ash. Nuclear reactors can produce tremendous heat which can be utilized for the production of electricity with high conversion efficiency. Also, due to depletion in fossil fuels, there will be a great demand for alternative cleaner energy resource such as hydrogen. Hydrogen production processes such as thermochemical water splitting and electrolysis require temperatures above 750°C. This high-temperature heat can be obtained from nuclear reactors. But present operational nuclear reactors have maximum outlet temperatures between 300°C and 650°C. 1 Hence, the hydrogen production plant is considered as a major unit coupled with nextgeneration nuclear reactors which are proposed for cogeneration of electricity and hydrogen. The possible heat transfer medium for next-generation nuclear rea...

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High temperature corrosion studies in molten salt-FLiNaK

Cited by 35 publications

References 14 publications

Temperature and radiation effects at the fluorine K-edge in LiF

Temperature and radiation effects at the fluorine K-edge in LiF

Investigation on Hot Corrosion Behaviour of Inconel 625 and Incoloy 800H Superalloys with YSZ‐Thermal Barrier Coating Under High‐Temperature Environment for Bioreactor Applications

Pretest in forced circulation molten salt heat transfer loop: Studies with thermia‐B

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