FLiNaK (LiF-NaF-KF: 46?5-11?5-42 mol.-%) is a promising candidate as high temperature coolant for next generation nuclear reactor coolants. Major technical challenge in implementation is the selection of structural material that can withstand corrosive nature of FLiNaK. Corrosion study of different alloys such as SS-316L, SS-317L, Inconel-625, Incoloy-800H, Hastelloy-B and Ni-201 was performed in FLiNaK salt. The tests were carried out in the temperature range of 650-850uC in graphite crucibles for 60 h under inert atmosphere. Weight loss of the alloy sample due to corrosion was measured, and corrosion rate was estimated. The salt composition after corrosion was analysed by inductively coupled plasma spectroscopy coupled with atomic emission spectroscopy. The surface morphology of the alloy samples was analysed by scanning electron microscopy. Ni-201 and Hastelloy-B showed better resistance to corrosion than other alloys. Corrosion rate was found to increase with increase in Cr content in the alloy. List of symbolsA area of exposure, cm 2 C p specific heat, J kg 21 uC 21 t time of exposure, h T temperature, K W weight loss after corrosion, mg r density, kg m 23 r m density of the specimen, g cm 23
The largest network of fluid transportation in the world is through pipelines.During the transportation of fluids through pipes, several "fittings" are used in the piping system such as elbows, T-junctions, reducers, expanders, bends, couplings, valves, etc. The flow complexities in pipe fittings are accounted for the pressure drop in piping network design. The pressure drop is estimated using the loss coefficient or equivalent length method using standard charts. Computational fluid dynamics (CFD) is a reliable tool to estimate pressure drop and understand nonidealities in pipe fittings. The use of CFD in the advanced level course in transport phenomena/fluid flow for piping network design can help students to implement modern mathematical tools as well as evaluate standard protocols followed in the industries. In this article, an interactive teaching methodology has been implemented to investigate the hydrodynamics in various pipe fittings (elbow, bend, Tee, and reducer) by actually visualizing the flow. The three-dimensional flow visualization is used to demonstrate the nonidealities such as separation, swirling, dead zones, etc. The CFD simulations of pipe fittings provided a new learning experience to the students that would help them to predict the pressure drops in industrial piping network systems. The outcome from the students' survey showed that the proposed CFD methodology assisted them to gain a better understanding of conventional Chemical Engineering subjects of "Transport Phenomena" and "Fluid Dynamics" in an innovative way. K E Y W O R D Scomputational fluid dynamics, head loss coefficient, pipe fittings, turbulence models 1
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...
scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.
hi@scite.ai
10624 S. Eastern Ave., Ste. A-614
Henderson, NV 89052, USA
Copyright © 2024 scite LLC. All rights reserved.
Made with 💙 for researchers
Part of the Research Solutions Family.