Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor

Alatrash, Yazan; Kang, Han-Ok; Yoon, Hyun-Gi; Seo, Kyoungwoo; Chi, Dae-Young; Yoon, Juhyeon

doi:10.1016/j.nucengdes.2015.01.018

Cited by 14 publications

(5 citation statements)

References 5 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Jian et al (2012) studied the change in the flow state of the nuclear reactor coolant pump during the coast-down process in the small break loss of coolant accident. Alatrash et al (2015) conducted a test and analyzed the coast-down process of the nuclear reactor coolant pump and verified the consistency of the simulation prediction and the experiment by comparing the simulation results with the experimental data. Farhadi (2010) proposed an analytical model which can be used to calculate the flow velocity of the nuclear reactor coolant pump during the coast-down process and found the detailed flow characteristic of the nuclear reactor coolant pump.…”

Section: Introductionmentioning

confidence: 83%

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

et al. 2020

View full text Add to dashboard Cite

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.

show abstract

Section: Introductionmentioning

confidence: 83%

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

et al. 2020

View full text Add to dashboard Cite

show abstract

“…Alatrash, Y. [12] conducted an experimental study of the inertial pumping capability during the coastdown period to confirm whether the coastdown half time requirement given by safety analyses is being satisfied. In the modular modeling system(MMS) simulation model, all of the design data that affect the pump coastdown behavior are reflected.…”

Section: Introductionmentioning

confidence: 99%

Mathematical Modelling Forecast on the Idling Transient Characteristic of Reactor Coolant Pump

Wang

Xie

et al. 2019

Processes

View full text Add to dashboard Cite

The idling behavior of the reactor coolant pump is referred to as an important indicator of the safe operation of the nuclear power system, while the idling transition process under the power failure accident condition is developed as a transient flow process. In this process, the parameters such as the flow rate, speed, and head of the reactor coolant pump are all nonlinear changes. In order to ensure the optimal idling behavior of the reactor coolant pump under the power cutoff accident condition, this manuscript takes the guide vanes of the AP1000 reactor coolant pump as the subject of this study. In this paper, the mathematical model of idling speed and flow characteristic curve of reactor coolant pump under the power failure condition were proposed, while the hydraulic modeling database of different vane structure parameters was modeled based on the orthogonal optimization schemes. Furthermore, based on the mathematical modeling framework of multiple linear regressions, the mathematical relationship of the hydraulic performance of each guide vane in different parameters was predicted. The derived model was verified with the idling test data.

show abstract

“…By establishing a mathematical start-up model for the primary circuit cooling system, Farhadi et al [7][8][9] studied the effects of the ratio between the inertial energy of the unit and the fluid mass inertia energy of the pipe coolant during the start-up process of the nuclear reactor coolant pump. Whether the pumping capability meets the coast-down half time requirement as prescribed by safety analyses during the coast-down period was studied by Alatrash et al [10] using experiments. Yonggang [11][12][13] studied the third and fourth generation nuclear main pumps, including gas-liquid two-phase flow and structural optimization.…”

Section: Introductionmentioning

confidence: 99%

The Influence and Optimization of Geometrical Parameters on Coast-Down Characteristics of Nuclear Reactor Coolant Pumps

Zhao

Wang

et al. 2019

Processes

View full text Add to dashboard Cite

Coast-down characteristics are the crucial safety evaluation factors of nuclear reactor coolant pumps. The energy stored at the highest moment of inertia of the reactor coolant pump unit is utilized to maintain a normal coolant supply to the core of the cooling loop system for a short period of time during the coast-down transition. As a result of the high inertia moment of the rotor system, the unit requires a high reliability of the nuclear reactor coolant pump and consumes considerable energy in the start-up and normal operation. This paper considers the operational characteristics of the coast-down transition process based on the existing hydraulic model of the nuclear reactor coolant pump. With the implementation of an orthogonal test, the hydraulic performance of the nuclear reactor coolant pump was optimized, and the optimal combination of impeller geometrical parameters was selected using multivariate linear regression to prolong the coast-down time of the reactor coolant pump and to avoid serious nuclear accidents.

show abstract

Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor

Cited by 14 publications

References 5 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

Mathematical Modelling Forecast on the Idling Transient Characteristic of Reactor Coolant Pump

The Influence and Optimization of Geometrical Parameters on Coast-Down Characteristics of Nuclear Reactor Coolant Pumps

Contact Info

Product

Resources

About