Control rod drop analysis by finite element method using fluid–structure interaction for a pressurized water reactor power plant

Yoon, Kyungho; Kim, J.Y.; Lee, K.H.; Lee, Y.H.; Kim, H.K.

doi:10.1016/j.nucengdes.2009.05.023

Cited by 26 publications

(5 citation statements)

References 8 publications

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“…The rod's drop-down experiment shows that control rod assembly falls into the buffer section in 1.24 s and at the speed of 2.67 m/s. The results calculated by the program are basically consistent with the data from rod's drop-down experiment [14,15], with a deviation less than 10%. Therefore the computing method of this paper is reliable and conservative.…”

Section: Development and Verification Of The Codesupporting

confidence: 79%

R&D on a Nonlinear Dynamics Analysis Code for the Drop Time of the Control Rod

Wang

Xie³

et al. 2017

Science and Technology of Nuclear Installations

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Whether the control rod can drop down in time is one of the important guarantees for the safe operation of the nuclear power plant. The drop-down process of the control rod is very complicated. For a long time, the researchers have done a lot of work on that, but it is hard to consider all the nonlinear factors. This paper considers the main factors together. Based on the theoretical analysis, we developed the nonlinear dynamics response analysis software for the nuclear power plant, which can be used to calculate the rod's drop-down time. Compared with the results of the experiments, the software we developed proves to be applicable and reliable.

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Section: Development and Verification Of The Codesupporting

confidence: 79%

R&D on a Nonlinear Dynamics Analysis Code for the Drop Time of the Control Rod

Wang

Xie³

et al. 2017

Science and Technology of Nuclear Installations

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“…This anal y sis model in cludes the struc ture and fluid parts, termed as a fluid and struc ture in ter ac tion (FSI). It was found that this method can simu late the fluid-struc ture cou pled al go rithm un der the core con di tions at an op er at ing tem per a ture [4]. This pa per pres ents a math e mat i cal model which per mits the de sign ers to study the ef fects of dif fer ent pa ram e ters on the scram time.…”

Section: Introductionmentioning

confidence: 98%

Numerical investigation of the deformation of a control rod system during a drop impact scenario in a typical material testing reactor

Alyan

Elkhatib

2019

Nucl Technol Radiat Prot

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The control rod drop analysis is very important for safety analysis. A mathematical model of the control rod for the ETRR-2 reactor is presented. A computer program by the Engineering Equation Solver has been developed for investigation of the impact force and the final dropping velocity of the rod. Also, buckling deformation stresses have been simulated using commercial software, ABAQUS/CAE release 6.14-5. This paper describes the theoretical results required to obtain the von Mises stress at maximum impact force during the control rod drop. The control rod velocity after the rod reached the reactor core bottom has been predicted which reached up to 3.8 ms?1 after a drop time equal to 0.41 s at the end of the reactor core height. The results showed that the maximum and minimum von Mises stresses are 90 MPa and 6.345 MPa at maximum and minimum impact force of 6625 N and 755.73 N, respectively.

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“…Due to the coupling of the dual effects of mechanical force and fluid resistance, the hydraulic buffer has a compact structure and ingenious design, so its application potential is great (Qin et al, 2018;Mingmin and Claus, 2013). So far, several researches have analyzed the control rod dropping program by simulated or experimental method (Yoon et al, 2009;Lin et al, 2017;Zhang et al, 2020;Zhang et al, 2021). However, the analysis of the subsequent buffer program during rod dropping, especially the relationship between the buffer performance and structural parameters, has not been systematically studied yet.…”

Section: Introductionmentioning

confidence: 99%

Experimental Analysis and Performance Evaluation of Spider Hydraulic Buffer for Rod Dropping in Reactor

et al. 2022

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Control rod drop is one of the key measures for the safe shutdown of the reactor. The two important evaluation indicators of the drop process are the drop time-length and the maximum impact force. By theoretical and experimental methods, this paper analyzes the influencing factors and evaluates the performance of a new type of spider hydraulic buffer with compact structure and ingenious design, which couples mechanical force and fluid resistance. First, through experiments, it is found that the real-time curve of the maximum impact force often has a bimodal structure. And the double peaks vary with the change of the internal structure of the hydraulic buffer. Secondly, since there are many variables about the structure (aperture, position, quantity, piston stroke et al.), in order to consider their influence on the maximum impact force, an equivalent ongoing flow area of the drain holes is introduced. It suggested that when the flow area of the working holes which can be covered by the stroke is close to the flow area of the remaining holes, the impact force tends to appear a minimum value. A relationship between the maximum impact force and the structure is proposed accordingly. Finally, this paper proposes a quantitative evaluation method for comprehensive buffering performance, in which the comprehensive performance evaluation factor η (0<η < 1) takes into account both the maximum impact force and the drop time. The smaller the maximum impact force and the rod drop time-length, the closer the evaluation factor η is to 1, indicating that the buffering performance is better. The research in this paper will not only help to further understand the mechanism of the drop rod buffering process, but also contribute to the structural optimization of the subsequent spider hydraulic buffer.

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Control rod drop analysis by finite element method using fluid–structure interaction for a pressurized water reactor power plant

Cited by 26 publications

References 8 publications

R&D on a Nonlinear Dynamics Analysis Code for the Drop Time of the Control Rod

R&D on a Nonlinear Dynamics Analysis Code for the Drop Time of the Control Rod

Numerical investigation of the deformation of a control rod system during a drop impact scenario in a typical material testing reactor

Experimental Analysis and Performance Evaluation of Spider Hydraulic Buffer for Rod Dropping in Reactor

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