Analytical studies of the heat removal capability of a passive auxiliary feedwater system (PAFS)

Cho, Yun-Je; Bae, Sung-Won; Bae, Byoung-Uhn; Kim, Seok; Kang, Kyoung-Ho; Yun, Byong-Jo

doi:10.1016/j.nucengdes.2012.03.046

Cited by 28 publications

(5 citation statements)

References 4 publications

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“…Similarly, the passive systems are used in third-generation reactors all over the world, such as AP1000 [3,4], VVER1000 [5], and APR1000 [6]. e passive safety system can not only improve the safety performance but also reduce the cost of the NPPs, making nuclear power a safer and economical choice.…”

Section: Prefacementioning

confidence: 99%

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

Chu

et al. 2021

Science and Technology of Nuclear Installations

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In response to a station blackout accident similar to the Fukushima nuclear accident, China’s Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based on the two-phase natural circulation principle, the system is designed to bring out long-term core residual heat after an accident to ensure that the reactor is in a safe state. The steady-state characteristic test and transient start and run test of the PRS were carried out on the integrated experiment bench named ESPRIT. The experiment results show that the PRS can establish natural circulation and discharge residual heat of the first loop. China’s Fuqing no. 5 nuclear power plant completed the installation of the PRS in September 2019 and carried out commissioning work in October. This debugging is the first real-world debugging of the new design. This paper introduces the design process of the PRS debugging scheme.

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Section: Prefacementioning

confidence: 99%

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

Chu

et al. 2021

Science and Technology of Nuclear Installations

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“…3 shows the PHRS node graph. It is designed according to the PAFS of APR+ (Cho et al, 2012). The nearly-horizontal heat exchanger tubes 408 P submerged inside the PCCT 432 P and 434 P. During normal operation, the PHRS isolation valve 413 V would be closed.…”

Section: Pafs Modelingmentioning

confidence: 99%

The investigation of Passive Accident Mitigation Scheme for advanced PWR NPP

Shi

Fang

Wang

et al. 2015

Annals of Nuclear Energy

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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%

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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Analytical studies of the heat removal capability of a passive auxiliary feedwater system (PAFS)

Cited by 28 publications

References 4 publications

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

The investigation of Passive Accident Mitigation Scheme for advanced PWR NPP

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

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