Investigation into the effects of a coastdown flow on the characteristics of early stage cooling of the reactor pool in KALIMER-600

Han, Jeongho; Lee, Tae‐Ho; Eoh, Jaehyuk; Kim, Seong-O

doi:10.1016/j.anucene.2009.07.004

Cited by 18 publications

(7 citation statements)

References 3 publications

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“…Gao et al (2011) deduced the pump speed transient equation of the nuclear reactor coolant pump in the coast-down process based on the moment balance equation of the nuclear reactor coolant pump and verified the equation through a test. Han et al (2009) explored the effect of cooling performance for KALIMER-600 caused by the nuclear reactor coolant pump with the flywheels of various moments of inertia in a power failure condition. Jiang et al (2014) proposed a calculation model for the preliminary design calculation of the nuclear reactor coolant pump and validated the analysis.…”

Section: Introductionmentioning

confidence: 99%

An Experimental Study on Transient Characteristics of a Nuclear Reactor Coolant Pump in Coast-Down Process Under Power Failure Condition

et al. 2020

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In order to study the transient characteristics of a nuclear reactor coolant pump in coastdown process under power failure condition, a transient test device for the nuclear reactor coolant pump is set up. This study investigates the effects of the rotor of the nuclear reactor coolant pump and the circuit characteristics on the nuclear reactor coolant pump during the coast-down process by changing the rotary inertia of the flywheel and the resistance of the pipe system. The results show that the greater the moment of inertia is, the more slowly rotational speed, flow, and lift get down in the same coast-down period. The change in the pipe resistance has little effect on the rate of decline in the coast-down process, but it has a great influence on the descent speed of the flow rate and lift. When the pipe resistance is small, the corresponding flow rate decreases faster, but it is slower for the corresponding lift. The results are of great significance in controlling the stability and reliability of the nuclear reactor coolant pump in the coast-down process.

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Section: Introductionmentioning

confidence: 99%

An Experimental Study on Transient Characteristics of a Nuclear Reactor Coolant Pump in Coast-Down Process Under Power Failure Condition

et al. 2020

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“…Wang et al [7] explored the gas content effect of RCP with power shutting down transitions. Han et al [8] simulated the coastdown flow of RCP during a loss of heat sink accident. However, the understanding about flow behaviors of RCP under natural circulation condition is insufficient.…”

Section: Introductionmentioning

confidence: 99%

Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition

Lei

Hao

et al. 2019

Science and Technology of Nuclear Installations

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Passive safety system is the core feature of advanced nuclear power plant (NPP). It is a research hotspot to fulfill the function of passive safety system by improving the NPP natural circulation capacity. Considering that the flow behaviors of stopped pump pose a significant effect on natural circulation, both experimental and computational fluid dynamics (CFD) methods were performed to investigate the flow behaviors of a NPP centrifugal pump under natural circulation condition with a low flow rate. Since the pump structure may lead to different flows depending on the flow direction, an experimental loop was set up to measure the pressure drop and loss coefficient of the stopped pump for different flow directions. The experimental results show that the pressure drop of reverse direction is significantly greater than that of forward direction in same Reynolds number. In addition, the loss coefficient changes slightly while the Reynolds number is greater than 8 × 104; however, the coefficients show rapid increase with the decrease in Reynolds number under lower Reynolds number condition. According to the experimental data, an empirical correlation of the pump loss coefficient is obtained. A CFD analysis was also performed to simulate the experiment. The simulation provides a good accuracy with the experimental results. Furthermore, the internal flow field distributions are obtained. It is observed that the interface regions of main components in pump contribute to the most pressure losses. Significant differences are also observed in the flow field between forward and reverse condition. It is noted that the local flows vary with different Reynolds numbers. The study shows that the experimental and CFD methods are beneficial to enhance the understanding of pump internal flow behaviors.

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“…Han et al. 6 vigorously studied the coastdown flow transient by employing various flywheels focusing on early-stage characteristics of cooling of the reactor pool in KALIMER 600. The various factors like core peak temperature, flywheel size, and decay heat exchanger initialization were considered for the best design value for coastdown time and the decision was made of 25 s.…”

Section: Introductionmentioning

confidence: 99%

An improved core thermal-hydraulic model for coastdown transient in pressurized water reactor

Ahmad

Arshad

Tahir

et al. 2017

Proceedings of the Institution of Mechanical Engineers, Part A:

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The safety of the nuclear reactor revolves around the accurate analysis of rapid flow transient for the design and manufacturing of reactor coolant pumps. In this article, the coastdown transient initiated by the loss of offsite power is simulated. In this case, the pumps are operated by the inertia of the flywheel, therefore, the reliable operation of reactor coolant pumps is the key to the safety of the nuclear reactor. A new hydraulic, as well as the thermal model, is developed for simulating various core parameters during the coastdown period. The present hydraulic model accounts for both the pump half-time and the loop half-time, which is used to increase the accuracy of predicted results over a longer period of time. The results predicted by the hydraulic model are incorporated into a thermal model, which also includes the decay heat following the reactor shutdown. This new model depends upon the core time constant, loop time constant, pump half-time, and hydraulic constant coefficient. The predicted results of flow rate, pressure, temperature, and departure from nucleate boiling ratio are compared with the experimental data and have found good agreement between the two cases. Finally, the departure from nucleate boiling ratio shows that the transient behavior of the reactor is moving toward safety.

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Investigation into the effects of a coastdown flow on the characteristics of early stage cooling of the reactor pool in KALIMER-600

Cited by 18 publications

References 3 publications

An Experimental Study on Transient Characteristics of a Nuclear Reactor Coolant Pump in Coast-Down Process Under Power Failure Condition

An Experimental Study on Transient Characteristics of a Nuclear Reactor Coolant Pump in Coast-Down Process Under Power Failure Condition

Experimental and CFD Investigation on Flow Behaviors of a NPP Pump under Natural Circulation Condition

An improved core thermal-hydraulic model for coastdown transient in pressurized water reactor

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