Conversely, the collapse of cloud cavity causes a sudden reduction of lift and drag forces. When the large attached sheet cavity separates from the suction surface, the lift and drag forces increase substantially. Lift and drag forces increase approximately linearly with the development of sheet cavity. The force element analysis reveals that vortex structures induced by cavity evolution make the lift and drag forces fluctuation. The changed cavitation number also increases according to this rule. The evident temperature gradient exists in the vicinity of the closure line, which leads the temperature drop to increasing gradually from the closure line to the center of the cavity. The distribution of changed cavitation number is consistent with the cavity shape. A cavitation model is extended to investigate the thermal effect, and a shear stress transfer–partially averaged Navier–Stokes turbulence model is adopted to simulate the cavitating turbulent flow. This study aims to investigate the evolution of transient force and energy features in a thermo-sensitive cavitating flow around a hydrofoil. The prospects of using the developed nuclear magnetic flowmeter-relaxometer design in the nuclear reactor first circuit are shown. It is found that the measurement error for these parameters does not exceed 1%. Investigations of coolant flow parameters (consumption and relaxation times) inside the pipeline have been carried out. Methods for measuring the coolant flow’s longitudinal T1 and transverse T2 relaxation times are presented. A new nuclear magnetic flowmeter design has been developed using a modulation technique for nuclear magnetic resonance signal recording. New difficulties are noted as emerging when using pulsed nuclear magnetic flowmeters designs developed for measuring hydrocarbons, water, biological compounds consumption, and condition control. It has been found that nuclear magnetic flowmeters can solve these problems. Problems arising during coolant consumption control using various flowmeters models in the nuclear reactor primary circuit are considered.
ULTIMATE TAP TITANS 2 OPTIMIZER 2.2 GENERATOR
It is shown that a coolant consumption measurement error decreases and its condition data availability increases the heat transfer efficiency and the electrical energy generation (without the nuclear reactor and steam generator design change). Nowadays, the real-time coolant’s condition control function is not implemented at stationary nuclear power plants or mobile nuclear power plants used in moving objects. Additionally, the need to control the coolant condition in the current flow inside the pipeline is shown. The necessity of coolant flow consumption measurement accuracy increase in the nuclear reactor primary circuit has been substantiated. The present investigation shows that the proposed flowmeter is very promising for liquid hydrogen measurement. Cavitation was not detected inside the proposed flowmeter up to a Reynolds number of 2.2 × 10⁶. It measures the flow rate of liquid hydrogen with up to 25.5% higher discharge coefficient and 83.7% lower loss coefficient compared to a corresponding perforated plate flowmeter. The proposed flowmeter is shorter than the standard Venturi nozzle by 67.2% and its loss coefficient is lower by up to 10.6%. The applied optimization technique results in significant improvements of the flowmeter design and performance.
Numerical simulation, as well as multidimensional and multi-objective optimization, was utilized in order to minimize the flowmeter's loss coefficient and the required installation length. The present research introduces a novel constriction type flowmeter with an optimized flow profile. The high permanent pressure losses may also cause cavitation.
However, their permanent pressure losses and installation length could significantly increase the manufacturing, installation, metering, maintenance, and replacement cost. Constriction type flowmeters could be a favorable candidate for liquid hydrogen. The wide spreading hydrogen energy requires accurate flow measurement.
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