Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor

Lee, Young-Kyu; Lee, Jae-Han; Kim, Hoe-Woong; Kim, Sungkyun; Kim, Jong Bum

doi:10.1016/j.net.2016.12.004

Cited by 12 publications

(3 citation statements)

References 5 publications

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“…Once the earthquake is detected the RCS drops the MP into the core to achieve a safe shutdown. This is done on the order of 1 second for FRs [10,23]. Thus, any large deformations after this shutdown state has occurred is of secondary importance.…”

Section: Static Deformation + Dynamic Excitationmentioning

confidence: 99%

Implementation and Comparison of Contact Models Within PIRAT for Nuclear Reactivity Control Systems

Bonney

Zabiego

2020

Journal of Vibration and Acoustics

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The reactivity control system is a vital safety system for a nuclear reactor. One of the most challenging aspects in the design of these systems is the operation during critical situations, in particular during earthquakes to safely shut-down the reactor. To study these situations, the toolbox python Implementation for Reliability Assessment Tools (PIRAT) is used to model two types of excitation: single frequency and realistic. The main focus of this work is the comparison of the implementation of the contact models used to describe the interaction between the subsystems. For the dynamic tool in PIRAT (dynamic Euler–Bernoulli for seismic event (DEBSE)), this is done with a two-stage linear spring or Lankarani and Nikravesh-based models. For the sine excitation, the results show four distinct response types with the maximum displacement varying between the models. Low-frequency excitation showed little variance while higher frequency excitation showed large variations. The realistic excitation, however, did not show these variations and showed nearly identical results for the contact models tested. This gives confidence in the simulations since the user selected contact model did not greatly affect the simulation results for a realistic excitation.

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Section: Static Deformation + Dynamic Excitationmentioning

confidence: 99%

Implementation and Comparison of Contact Models Within PIRAT for Nuclear Reactivity Control Systems

Bonney

Zabiego

2020

Journal of Vibration and Acoustics

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“…[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]. A passive core cooling system is proposed [2].…”

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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“…In Training, Research, Isotopes, General Atomics (TRIGA) research reactor, the control rods that containing a solid boron carbide (B4C) [2] is used to control reactivity during changing in reactor power level and as the main safety mechanism for reactor shut-down. Each control rod is connected to its drive unit called a control rod drive mechanism (CRDM) [3][4]. The CRDM is the hardware unit consists of a motor with reducing gearing a rack-and-pinion to lift (or lowering) the control rods.…”

Section: Introductionmentioning

confidence: 99%

An improved control rod selection algorithm for core power control at TRIGA PUSPATI Reactor

Minhat

Subha

Hassan

et al. 2020

JMES

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The 1 MWth TRIGA PUSPATI Reactor known as RTP undergoes more than 37 years of operation in Malaysia. The current core power control utilized Feedback Control Algorithm (FCA) and a conventional Control Rod Selection Algorithm (CRSA). However, the current power tracking performance suffers and increase the workload on Control Rod Drive Mechanism (CRDM) if the range between minimum and maximum rod worth value for each control rod has a significant difference. Thus, it is requiring much time to keep the core power stable at the power demand value within the acceptable error bands for the safety requirement of the RTP. In conventional CRSA, regardless of the rod worth value, the lowest position of the control rod is selected for up-movement to regulate the reactor power with 2% chattering error. To improve this method, a new CRSA is introduced named Single Control Absorbing Rod (SCAR). In SCAR, only one rod with highest reactivity worth value will be selected for coast tuning during transient and the lowest reactivity worth value will be selected for fine-tuning rod movement during steady-state. The simulation model of the reactor core is represented based on point kinetics model, thermal-hydraulic models and reactivity model. The conventional CRSA model included with control rod position dynamic model and actual reactivity worth curve data from RTP. The FCA controller is designed based on Proportional-Integral (PI) controller using MATLAB Simulink simulation. The core power control system is represented by the integration of a reactor core model, CRSA model and FCA controller. To manifest the effectiveness of the proposed SCAR algorithm, the results are compared to the conventional CRSA in both simulation and experimentation. Overall, the results shows that the SCAR algorithm offers generally better results than the conventional CRSA with the reduction in rising time up to 44%, workload up to 35%, settling time up to 26% and chattering error up to 18% of the nominal value.

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Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor

Cited by 12 publications

References 5 publications

Implementation and Comparison of Contact Models Within PIRAT for Nuclear Reactivity Control Systems

Implementation and Comparison of Contact Models Within PIRAT for Nuclear Reactivity Control Systems

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

An improved control rod selection algorithm for core power control at TRIGA PUSPATI Reactor

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