Experimental evaluation of re-entrainment from wet scrubber filtered containment venting systems

Advanced heavy water reactor (AHWR) is a natural circulation-based, light water-cooled, heavy water-moderated pressure tube type of nuclear reactor. In AHWR, the steam separation takes place in horizontal steam drums purely based on gravity separation principle. It is a known fact that efficiency of gravity separation is affected by the carryover phenomenon, i.e., conveyance of water droplets by the steam. To minimize the carryover, it is advised to reduce the superficial velocities of phases. Lowering the flow velocities also results in to lower pressure drop, which is very much desired. However, careful attention must be given to carryover phenomenon during design. An experimental test facility known as air–water loop (AWL) simulating the scaled down steam drum of AHWR with air–water mixture has been designed and experimental work performed on carryover phenomenon is presented here. Comparison of measured entrainment fraction with existing correlations and other visual observations are described. Numerical simulations with Euler–Lagrangian method have been carried out for which droplet size distribution measured experimentally is used as an input.

Experimental Investigations on Carryover in a Gravity Separation-Based Steam Drum

Experimental and theoretical investigation on pool entrainment under small air flow rate

Flow structures associated with CSRDM shroud tube and control rod assembly: A combined experimental and simulation study

The invention provides a comprehensive monitoring system and method for a spent fuel pool in a nuclear power station. The comprehensive monitoring system comprises: acquisition assemblies used for acquiring and transmitting temperature signals of a plurality of elevations of the pool and a plurality of thermal diffusion principle-based switching value liquid level signals; analog quantity liquid level detectors used for detecting the liquid level of the spent fuel pool; and a processing and transmitting unit used for receiving the temperature signals, the thermal-diffusion type liquid level signals and liquid level signals of the analog quantity liquid level detectors, judging whether the received temperature signals are effective water temperature signals or not according to the receivedthermal-diffusion type liquid level signals, and displaying the liquid level height and the water temperature of the pool. The liquid level of the spent fuel pool is measured by adopting diversified measurement technologies such as thermal-diffusion type and guided wave radar measurement technologies, so the liquid level of the spent fuel pool can be accurately obtained under various working conditions, and the safety of the spent fuel pool is ensured; meanwhile, the non-heating element for thermal-diffusion type liquid level measurement can measure water temperatures of different elevations at the same time, so whether hot spots exist at different elevations of the pool or not can be accurately detected and reliability is high.

Comprehensive monitoring system and method for spent fuel pool in nuclear power station

An experimental study of pool entrainment with side exit

The utility model provides a test device that is used for pond formula to smuggle mechanism research secretly, includes: erect the main part container of placing, input device sets up the lower part of main part container, with to input gas and water in the main part container, aqueous vapor separator sets up the upper portion of main part container to main part container exhaust water vapor mixture be will follow and water and gas will be separated into, and collection bearing water tank, with aqueous vapor separator intercommunication is followed in order to collect the weight of the water that the aqueous vapor separator discharged water and the first astronautic research institute for measurement and test collected. This test device can guarantee that test conditions is the same with prototype nuclear reactor with experimental operating mode by furthest to acquire the tentation data that more approaches the prototype reactor actual conditions. This test device can reduce testing equipment's figure, practices thrift experimentation cost, improves test efficiency.

A test device that is used for pond formula to smuggle mechanism research secretly

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An experimental study of pool entrainment with side exit

A test device that is used for pond formula to smuggle mechanism research secretly