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Rapid diagnostic method for transplutonium isotope production in high flux reactors

Nuclear science and Techniques 2023年第3期34卷 125-142页

作者： Qing-Quan Pan Qing-Fei Zhao Lian-Jie Wang Bang-Yang Xia Yun Cai Xiao-Jing Liu School of Nuclear Science and Engineering Shanghai Jiao Tong UniversityShanghai 200240China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610200China

Transplutonium isotopes are scarce and need to be produced by irradiation in high flux ***,their production is inefficient,and optimization studies are *** study analyzes the physical nature of transplutonium isotope produc-tion using ^(252)Cf,^(244)Cm,^(242)Cm,and ^(238)Pu as *** methods based on the Monte Carlo burnup calculation have the limitations of many calculations and cannot analyze the individual energy intervals in detail;thus,they cannot sup-port the refined evaluation,screening,and optimization of the irradiation *** understanding the physical nature and simplifying the complexity of the production process,we propose a rapid diagnostic method for evaluating radiation schemes based on the concepts“single energy interval value(SEIV)”and“energy spectrum total value(ESTV)”.The rapid diagnostic method not only avoids tedious burnup calculations,but also provides a direction for *** optimal irradiation schemes for producing ^(252)Cf,^(244)Cm,^(242)Cm,and ^(238)Pu are determined based on a rapid diagnostic *** irradiation schemes can significantly improve production *** with the initial scheme,the optimal scheme improved the production efficiency of ^(238)Pu by 7.41 times;^(242)Cm,11.98 times;^(244)Cm,65.20 times;and ^(252)Cf,15.08 ***,a refined analysis of transplutonium isotope production is conducted and provides a theoretical basis for improving production efficiency.

关键词： Transplutonium isotope Rapid diagnostic method Production optimization Single energy interval value Energy spectrum total value

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Research and design on the Control Rod Drive Mechanism Power Supply and Control Strategy for the Nuclear Power Plants Based on Silicon-Controlled Rectifier 10

Research and Design on the Control Rod Drive Mechanism Power...

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10th IEEE International Power Electronics and Motion Control Conference, IPEMC 2024 ECCE Asia

作者： Xu, A. Mingzhou Gao Zheng, B. Zhao, C. Zerun Ping Yang, D. Peng, E. Yusheng Science and Technology on Reactor System Design Technology Laboratory China Southwest Jiaotong University China

ISBN: (纸本)9798350351330

Due to the characteristics of large output current ripple and long current rise and fall times in the current rod control power supply basedsilicon-controlled rectifier, a decoupling nonlinear adaptive control is *** proposed control strategy can improve the rod control power supply of the speed of respond and the steady-state current accuracy. Practical application has shown that this method solves the output current ripple and the rise and fall time of the current, meeting the working requirements of rod control power supply in nuclear power plants. © 2024 IEEE.

关键词： Nuclear fuels

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Fretting Wear Characteristics of Nuclear Fuel Cladding in High-Temperature Pressurized Water

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Chinese Journal of Mechanical Engineering 2023年第4期36卷 326-338页

作者： Jun Wang Haojie Li Zhengyang Li Yujie Lei Quanyao Ren Yongjun Jiao Zhenbing Cai Key Lab of Advanced Technologies of Materials Tribology Research InstituteSouthwest Jiaotong UniversityChengdu 610031China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

In pressurized water reactor(PWR),fretting wear is one of the main causes of fuel assembly ***,the operation condition of cladding is complex and harsh.A unique fretting damage test equipment was developed and tested to simulate the fretting damage evolution process of cladding in the PWR *** can simulate the fretting wear experiment of PWR under different temperatures(maximum temperature is 350℃),displacement amplitude,vibration frequency,and normal *** fretting wear behavior of Zr-4 alloy under different temperature environments was *** addition,the evolution of wear scar morphology,profile,and wear volume was studied using an optical microscope(OM),scanning electron microscopy(SEM),and a 3D white light *** show that higher water temperature evidently decreased the cladding wear volume,the wear mechanism of Zr-4 cladding changed from abrasive wear to adhesive wear and the formation of an oxide layer on the wear scar reduced the wear volume and maximum wear depth.

关键词： Fretting wear Cladding High temperature and high pressure Zirconium alloy

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RESEARCH ON INTEGRATED VIBRATION ISOLATION AND VIBRATION ABSORPTION FOR PUMP EQUIPMENT 30

RESEARCH ON INTEGRATED VIBRATION ISOLATION AND VIBRATION ABS...

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30th International Congress on Sound and Vibration, ICSV 2024

作者： Zhaowen, Li Longqi, Cai Yu, Wang Lizhi, Liu Jianyong, Lai National Key Laboratory of Reactor System Design Technology Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789090390581

Pump equipment is the main source of vibration and noise during ship operation, and there are distinct characteristic line spectra at various transmission paths, which is not conducive to vibration reduction and noise control of ship system. Therefore, this paper focuses on a type of pump with significant vibration and prominent 50Hz characteristic line spectrum. It conducts research on integrated vibration isolation and vibration absorption based on floating raft isolation and dynamic vibration absorbers. The feasibility of above scheme was verified by the research on floating raft structure design, research on dynamic vibration absorber parameters, and analysis of vibration reduction and absorption effects. This paper provides a great measure to reduce the delivery of vibration and control line spectrum feature of one frequency of pump equipment. © 2024 Proceedings of the International Congress on Sound and Vibration. All rights reserved.

关键词： Vibration analysis

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A Tutorial on Quantized Feedback Control

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IEEE/CAA Journal of Automatica Sinica 2024年第1期11卷 5-17页

作者： Minyue Fu IEEE the School of System Design and Intelligent Manufacturing Shenzhen Key Laboratory of Control Theory and Intelligent Systems and Centre for Control Science and TechnologySouthern University of Science and TechnologyShenzhen 518055China

In this tutorial paper, we explore the field of quantized feedback control, which has gained significant attention due to the growing prevalence of networked control systems. These systems require the transmission of feedback information, such as measurements and control signals, over digital networks, presenting novel challenges in estimation and control design. Our examination encompasses various topics, including the minimal information needed for effective feedback control, the design of quantizers, strategies for quantized control design and estimation,achieving consensus control with quantized data, and the pursuit of high-precision tracking using quantized measurements.

关键词： Consensus control high-precision control networked control quantized estimation quantized feedback control robust control

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A NUMERICAL SIMULATION METHOD FOR THE VIBRATION REDUCTION OF MR ISOLATOR BASED ON IMPEDANCE TEST 30

A NUMERICAL SIMULATION METHOD FOR THE VIBRATION REDUCTION OF...

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30th International Congress on Sound and Vibration, ICSV 2024

作者： Wenzheng, Zhang Peng, Xiangfeng Zhihao, Yuan Guojiang, Liao Xiaozhou, Jiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789090390581

It’s important to choose suitable method to simulate the vibration reduction of the isolators. For a long time, scholars and engineers have been working hard to reduce the error between numerical simulation and experimental results of the vibration level drop of the isolators. Due to the standing wave effect and the limitations of analytical models, it is difficult to simulate the vibration level drop of isolators well solely based on dynamic stiffness or damping. In this paper, an analysis model for the vibration reduction effect of metal-rubber (MR) vibration isolators based on impedance test data is established. The origin impedance and cross point impedance data is tested on the testing platform. The four-terminal parameter method is applied to calculate the stiffness and damping value of the MR vibration isolators. The calculation results show that compared with commonly used numerical simulation methods in the past, the model based on frequency dependent stiffness and damping can further reduce the error between the numerical simulation and the experimental results. © 2024 Proceedings of the International Congress on Sound and Vibration. All rights reserved.

关键词： Damping

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NUMERICAL INVESTIGATION ON THE THERMAL-HYDRAULIC AND FIV CHARACTERISTICS IN LBE-COOLED HELICAL CRUCIFORM FUEL AND WIRE-WRAPPED FUEL 31

NUMERICAL INVESTIGATION ON THE THERMAL-HYDRAULIC AND FIV CHA...

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2024 31st International Conference on Nuclear Engineering, ICONE 2024

作者： Qi, Zhang Haoyu, Wang Cao, Junxian Yuanming, Li Chenxi, Li Zhenhai, Liu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9780791888261

The lead bismuth eutectic (LBE) cooled fast reactor in one of the General 4 advanced reactors, which plays significant role in the nuclear fuel cycle. In the recent years, the wire-wrapped fuel with four wires surrounds the cylindrical fuel is developed and promoted, which may be accept by the LBE-cooled fast reactor. The helical cruciform fuel of the Lightbridge corporation has similar geometrical features with the wire-wrapped fuel. The cross-section of helical cruciform fuel consists of the convex blades and the concave elbows, and the cross-section is rotated around the axis. The blade and elbow of helical cruciform fuel function as the wires while they are part of the nuclear fuel. In the present work, the comparison on the thermal-hydraulic and flow-induced vibration (FIV) characteristics of the helical cruciform fuel and wire-wrapped fuel is carried out by numerical simulation. The fluid-structure interaction is solved by the coupling between the fluid and solid domains, and the transient turbulence fluctuation is solved by large eddy simulation (LES). The results show that the convective heat transfer is enhanced by the spiral structures even though the hot spot phenomenon is caused simultaneously. The hot spot temperature of the helical cruciform fuel is larger than the wire-wrapped fuel duo to the non-uniform distributed heat flux. As the coolant in the flow channel is blocked by the blades and wires, the directional transverse flow is generated and thus the transverse mixing is enhanced. The one-way mixing with opposite direction occurs in the two sides of the single rod. There are similarities in the FIV characteristics for the spiral shaped fuels. The maximum vibration displacement and dominant vibration frequency of the helical cruciform fuel and wire-wrapped fuel are almost the same. © 2024 by ASME.

关键词： Fluid structure interaction

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STUDY ON DYNAMIC RESPONSE OF reactor CORE BARREL UNDER PUMP-INDUCED PULSATING PRESSURE 30

STUDY ON DYNAMIC RESPONSE OF REACTOR CORE BARREL UNDER PUMP-...

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30th International Congress on Sound and Vibration, ICSV 2024

作者： Ye, Xianhui Cai, Fengchun Huang, Xuan Feng, Zhipeng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9789090390581

The flow-induced vibration (FIV) problem is widely present in nuclear power plants and has caused numerous engineering accidents. Therefore, it has been highly valued by the nuclear engineering community for a long time. The pump-induced pulsating pressure is an important excitation source of FIV. The characteristics of pump-induced pulsating pressure are periodic, it may cause resonance and have the adverse impact on the fatigue life of reactor coolant system. In order to study the vibration of reactor core barrel (CB) of newly designed HPR1000 (Hua-long Pressurized reactor) under pump-induced pulsating pressure, the finite element model of CB is established and the dynamic response characteristics are analyzed. Combined with turbulent excitation, the influence of CB under flow induced load was comprehensively evaluated .The stress analysis shows that the maximum stress of FIV at each position of CB is less than the fatigue stress limit, and the structure is safe. However, for the newly designed reactor or the replacement of the reactor coolant pump, the pump-induced vibration of the CB and reactor internal should be paid enough attention to. © 2024 Proceedings of the International Congress on Sound and Vibration. All rights reserved.

关键词： Stress analysis

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A numerical method for predicting bursting strength of composite rocket motor case considering filament winding process-induced stress

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Chinese Journal of Aeronautics 2025年第2期38卷 505-518页

作者： Jiqiu LIANG Fei ZHAO Dan WU Anxin DING Hubei Key Laboratory of Advanced Aerospace Propulsion Technology Wuhan 430040China System Design Institute of Hubei Aerospace Technology Academy Wuhan 430040China School of Materials Science and Engineering Wuhan University of TechnologyWuhan 430070China State Key Laboratory of Advanced Technology for Materials Synthesis and Processing Wuhan University of TechnologyWuhan 430070China

A numerical method to predict the bursting strength of filament wound composite rocket motor case is proposed *** method can evaluate the longitudinal stress evolution of each composite layer as impregnated filaments with fiber tension are wound layer by layer,and consider the effects of accumulated stress and deformation during filament winding on the bursting strength of composite ***∅520 mm composite cases as a case study,the filament-winding-process-induced stress and deformation as well as progressive damage behavior are numerically predicted,followed by a comparison with experimental *** numerical results show that the predicted bursting pressures for composite cases manufactured on the mandrels with and without a flexible component are 14.20 MPa and 21.40 MPa,*** values exhibit slight deviation from the measured pressures of 13.50 MPa and 21.57 ***,the predicted damage locations,situated respectively in the dome and cylinder,agree well with the experimental *** observations indicate that use of flexible component reduces the load-bearing capacity of the ***,it validates the reliability and accuracy of the proposed numerical method in predicting the bursting strength of composite cases.

关键词： Composite case Fiber tension Bursting strengt hProgressive damage analysis Filament winding

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Research on The FPGA Reconfiguration technology Based on RS Code for Nuclear Applications 15

Research on The FPGA Reconfiguration Technology Based on RS ...

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15th IEEE Global Reliability and Prognostics and Health Management Conference, PHM-Beijing 2024

作者： Chen, Qi Wang, Fanyu He, Jinyu Zhao, Yang Wang, Heng Huang, Qichang Lei, Minjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (数字)9798350354010

ISBN: (纸本)9798350354010

Field Programmable Gate Array (FPGA) is now widely used in nuclear safety Instrumentation and Control (I&C) systems and operates core features like communication, signal capturing and processing, peripheral controlling etc. Those features are crucial to the entire system, which means the state of the FPGA is vital to the system as well. In nuclear I&C industry, single event effect (SEE) is a common hazard faced by the nuclear facilities which are exposed to the high radiation environment, because it may cause register upsets on static random-access memory (SRAM) devices and interfere the well-functioning of them. One popular method to solve this issue is fault diagnose, while this method only finds out the errors, not corrects them. To improve the solution, forward error correction technology, which is widely used in communication industry, is proposed to combine with the FPGA reconfiguration to check and rectify the upsets. Reed-Solomon (RS) Code is chosen to reinforce the core configuration data and to correct the faults by reconfiguration when diagnose problems occurs. Experiment was taken on the demo board to verify the viability of this strategy. The results indicate that this strategy can improve the FPGA against single event upset (SEU), thereby increase the system reliability in this aspect. © 2024 IEEE.

关键词： Forward error correction

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