Passive Containment Cooling System (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a severe accident scenario with release of non-condensable gas

Paladino, Domenico; Dreier, J.

doi:10.1016/j.nucengdes.2012.03.006

Cited by 5 publications

(3 citation statements)

References 4 publications

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“…Before the accident of nuclear power plant in Fukushima Daiichi, the concept of passive safety systems had been developed and introduced into the latest NPPs such as the ESBWR and the AP1000 [1]. Generation III+ reactor designs (including the AP1000) have been equipped with passive safety systems [4,5], which is the result of the evolution of safety technology design of nuclear power plants [6].…”

Section: Introduction mentioning

confidence: 99%

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An Experimental Analysis on Nusselt Number of Natural Circulation Flow in Transient Condition Based on the Height Differences between Heater and Cooler

et al. 2018

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A better understanding on the phenomenon of natural circulation flow for cooling systems is necessary prior to improving the safety of nuclear power plant, not only in normal operation but also in accident conditions. One way to understand this phenomenon is by analyzing the Nusselt number in various geometrical dimensions through experimentation. The purpose of this study is to understand natural circulation phenomenon in transient condition by varying height differences between heater and cooler. To achieve this purpose, an experiment apparatus called NC-Queen was developed and arranged to enable three variations of height differences between heater and cooler, i.e., 1.4 m, 1.0 m, and 0.3 m. It is made of a stainless steel tube with a diameter of 1 inch, arranged in rectangular shape 6.4 m in length, and uses water as coolant. The initial temperature of the heater was set at 90 °C. The Nusselt number was obtained by calculating the flow rate as a function of transient temperature. The results confirm that height differences affect thermal properties and flow region based kinetics characteristics of water. In initial condition, decreasing height difference from 1.4 m to 1.0 m resulted in flow rate reduction of 16.7 %, while decreasing height difference from 1.4 m to 0.3 m resulted in a 39.1 % flow rate reduction. In final condition, the flow rate reductions were 75 % and 82.6 %, respectively. Meanwhile, in initial condition, the Nusselt number for height difference reduction from 1.4 m to 1.0 m and from 1.4 m to 0.3 m decreased by 30.5 % and 74.6 %, respectively, while for final condition, the Nusselt number decreased by 11.9 % and 67.4 %, respectively. The new constants in relationship between Nusselt number and the height difference are a = 20.06 and b = 0.56. The dominance of turbulent flow provides a good safety margin with indications of the large amount of heat released.

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Section: Introduction mentioning

confidence: 99%

“…For the two flow conditions, equation 5can be used as a general representation of flow conditions. (5) with C, m and n being constant number generated from experimental data.…”

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confidence: 99%

An Experimental Analysis on Nusselt Number of Natural Circulation Flow in Transient Condition Based on the Height Differences between Heater and Cooler

et al. 2018

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“…Actually, before Fukushima Daiichi accident, the technology of reactor safety has been improved by introducing many innovations and realizing passive system to their safety features, such as AP1000 dan ESBWR [5]. Moreover, generation III+ nuclear reactor design, such as AP1000, have been equipped with passive safety system [6] as the result of the evolution in design development on nuclear safety technolgy [7]. The AP1000 is the first generation III+ NPP to obtain license from the United State -Nuclear Regulatory Commission (US -NRC) [8].…”

Section: Introduction mentioning

confidence: 99%

Preliminary Study on Mass Flow Rate in Passive Cooling Experimental Simulation During Transient Using NC-Queen Apparatus

et al. 2015

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The research related to thermal management has been significantly inreased, especially for NPP safety. The use of passive cooling systems both during the accident and operation become reliable in the advanced reactor safety systems. Therefore it should be enhanced through experimental studies to investigate heat transfer phenomenon of the heat decay in transient cooling condition. An investigation has been performed through experiment using an NC-Queen apparatus constructed with rectangular loop. Piping were consisting of tubes of SS316L with diameter, length, and width of 3/4 inch, 2.7 m, and 0.5 m respectively. The height between heater and cooler was 1.4 m. The experiment used initial water temperature at 70 o C, 80 o C, and 90 o C in heater area. Transient temperature was used as experimental data to calculate water mass flow rate. The results showed that the temperature in heater area and cooler area were decreasing of about 90.6% and 95.7% at initial temperatur of 80 o C, and of about 71.1% and 59.4% at initial temperature of 70 o C. Those results were at higher initial temperature of 90 o C compared with the initial temperature of 90 o C. The average of water mass flow rate increased 81.03% from initial temperatur of 70 o C. It was shown that the averages of removed heat in every second from water due to heat loss and cooler, were 3.51 watts, 5.06 watts and 6.85 watts respectively. The initial condition of heat stored in the water was quite different, but to the cooler heat removal capacity and heat loss was almost the same.

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2019

Linear and Non-Linear Stability Analysis in Boiling Water Reactors

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Passive Containment Cooling System (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a severe accident scenario with release of non-condensable gas

Cited by 5 publications

References 4 publications

An Experimental Analysis on Nusselt Number of Natural Circulation Flow in Transient Condition Based on the Height Differences between Heater and Cooler

An Experimental Analysis on Nusselt Number of Natural Circulation Flow in Transient Condition Based on the Height Differences between Heater and Cooler

Preliminary Study on Mass Flow Rate in Passive Cooling Experimental Simulation During Transient Using NC-Queen Apparatus

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