Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant

Kim, In Guk; Bang, In Cheol

doi:10.1016/j.expthermflusci.2017.03.013

Cited by 7 publications

(4 citation statements)

References 17 publications

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“…Author Details 1 The State Key Laboratory of Power Transmission Equipment & System Security and New Technology, Chongqing University, Chongqing 4000442, China. 2 Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China.…”

Section: Authors' Contributionsmentioning

confidence: 99%

“…The control rod drive mechanism (CRDM) is located inside the nuclear pressure vessel, which drives the neutron absorption control rod to move up and down, keeps at the commanding height, and drops when the power is off, thereby completing the reactor startup, power adjustment, and safe shutdown [1,2]. Nowadays, magnetic lifting CRDM is widely used in a pressurized water reactor.…”

Section: Introductionmentioning

confidence: 99%

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Wear Characteristics of the Nuclear Control Rod Drive Mechanism (CRDM) Movable Latch Serviced in High Temperature Water

et al. 2022

Chin. J. Mech. Eng.

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The current research of nuclear control rod drive mechanism (CRDM) movable latch only makes a simple measurement of wear mass. The wear volume and difference in various claw surfaces are ignored and the degradation mechanism of each claw surface is not clear. In this paper, a detailed degradation analysis was carried out on each claw surface of movable latch combined with wear result and worn morphology. Results indicate that the boundary of carbide is preferred for corrosion because carbide presents a nobler Volta potential compared to the metal matrix or boundary region. Due to the oscillation of drive shaft between the claw surfaces of movable latch, the dominant wear mechanism on the upper surface of claw (USC) and lower surface of claw (LSC) is plastic deformation caused by impact wear. Mechanical impact wear will cause the fragmentation of carbides because of the high hardness and low ductility of carbides. Corrosion promotes the broken carbides to fall off from the metal matrix. The generated fine carbides (abrasive particles) cause extra abrasive wear on USC when the movable brings the drive shaft upward or downward. As a result, USC has a higher wear volume than LSC. This research proposes a method to evaluate the wear on the whole movable latches using a 3D full-size scanner.

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Section: Authors' Contributionsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Wear Characteristics of the Nuclear Control Rod Drive Mechanism (CRDM) Movable Latch Serviced in High Temperature Water

et al. 2022

Chin. J. Mech. Eng.

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“…Refs. [1][2][3][4][5][6] introduced the research contents related to reliability optimization and the design of the CRDM of a nuclear reactor in recent years. The Korean Institute of atomic energy has developed and designed the prototype of the bottom mounted CRDM for the Kijang research reactor (KJRR) and compared the similarities and differences of some research reactors' CRDM [1].…”

Section: Introductionmentioning

confidence: 99%

“…The Korean Institute of atomic energy has developed and designed the prototype of the bottom mounted CRDM for the Kijang research reactor (KJRR) and compared the similarities and differences of some research reactors' CRDM [1]. A passive core cooling system is proposed [2]. The passive core cooling system is composed of a hydraulic CRDM and a hybrid control rod assembly to delay the fuel melting time and improve the safety of the nuclear power plant during the power failure accident of the nuclear power plant, which is finally verified by experiments.…”

Section: Introductionmentioning

confidence: 99%

Noise Reduction Method for the Vibration Signal of Reactor CRDM Based on CEEMDAACN-SK

Liu,

Li,

Zhu

et al. 2023

Electronics

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The reactor control rod drive mechanism (CRDM) controls the startup, shutdown and power of the reactor; it is one of the key pieces of equipment to ensure the normal operation of the reactor. CRDM is complex, mainly composed of stator, rotor, bearing, roller, etc. The characteristic analysis of the vibration monitoring signal is one of the important methods of the CRDM state evaluation. In view of the characteristics of large noise interference and the difficulty in analyzing the vibration monitoring signal of CRDM, this paper proposes a noise reduction method for the vibration signal of CRDM based on complete ensemble empirical mode decomposition with adaptive amplitude correction noise and spectral kurtosis (CEEMDAACN-SK), which can deeply reduce the vibration signal of CRDM. Firstly, the proposed CEEMDAACN algorithm is used to decompose the vibration signal of CRDM to obtain multiple intrinsic mode functions (IMF). Then, the spectral kurtosis of each IMF component is analyzed to obtain the spectral kurtosis map of each IMF component, which is compared with the spectral kurtosis map of the original signal. Finally, the denoising reconstruction of the signal is carried out to obtain the final denoising signal. Through experimental analysis, the performance of the proposed CEEMDAACN-SK denoising algorithm is better than the complete ensemble empirical mode decomposition with adaptive noise and spectral kurtosis (CEEMDAN-SK) algorithm in terms of results. The method proposed in this paper can be applied not only to the vibration signal noise reduction of CRDM, but also to other equipment and fields, such as nuclear power main circulation pump and the chemical industry.

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Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors

Seo

Kim

et al. 2018

Annals of Nuclear Energy

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Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant

Cited by 7 publications

References 17 publications

Wear Characteristics of the Nuclear Control Rod Drive Mechanism (CRDM) Movable Latch Serviced in High Temperature Water

Wear Characteristics of the Nuclear Control Rod Drive Mechanism (CRDM) Movable Latch Serviced in High Temperature Water

Noise Reduction Method for the Vibration Signal of Reactor CRDM Based on CEEMDAACN-SK

Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors

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