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2020 Vol. 41, No. 2

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Numerical Study on Characteristics of Single Droplet Impacting on Single Dry Flat Wire Mesh under Airflow Disturbance
Chen Bowen, Li Jingsong, Tian Ruifeng, Mao Feng, Lu Chuan, Wen Jiming
2020, 41(2): 1-5.
Abstract(349) PDF(239)
Abstract:
Mesh separators are widely used in industry. Based on the dynamic process of droplet impact on the mesh in this paper, the CLSVOF method is used to solve the problem of single droplet impact on the dry flat wire mesh. After reasonable simplification, a two-dimensional mathematical model of the singl...
Automatic Image Recognition and Analysis of Bubble Behavior in Rectangular Narrow Channel
He Xueqiang, Liu Hanzhou, Chen Deqi, Lu Qi
2020, 41(2): 6-10.
Abstract(362)
Abstract:
Aiming at the bubble dynamic behaviors generated during the boiling flow in the rectangular narrow channel, the high-speed camera was used to capture the bubble behaviors, and then the image processing technology was used to bubble recognition, and finally the characteristic parameters are extracted...
Error Analysis of LPD On-line Monitoring System in HPR 1000
Zhang Zhizhu, Liao Hongkuan, Li Qing, Gong Helin, Chen Zhang, Li Xiangyang, Liu Qiwei
2020, 41(2): 11-15.
Abstract(385)
Abstract:
LPD on-line monitoring system is adopted in nuclear power plants to calculate and display the real monitoring parameters such as linear power density (LPD) and hot spot factor, which can present the state of the reactor core accurately and in time, thus to improve the economy and safety of the nucle...
Analysis of Thorium-Loaded S&B Fuel Blocks Using RGPu and WGPu as Driver Fuels
Wang Jincheng, Huang Jie, Ding Ming
2020, 41(2): 16-21.
Abstract(183)
Abstract:
First-Principle Study of H Atom Adsorption on Zr(0001) Surface
Chen Wu, Zhang Hengquan, Ye Xiaofeng, Zeng Jing, Xiao Hongxing, Zhou Mengbing
2020, 41(2): 22-26.
Abstract(371)
Abstract:
The adsorption sites and mechanism of H atom on α-Zr(0001) surface were calculated and analyzed from microstructure, adsorption probability, adsorption energy, Mulliken charge population and density of state, and etc. based on the integration of Monte Carlo (MC) simulation and first-principle densit...
Effect of Nano-Y2O3 on Microstructure and Properties of ODS-HT9 Steel
Wu Kaixia, Zha Wusheng, Zhao Jiancheng, Tang Rui
2020, 41(2): 27-31.
Abstract(359)
Abstract:
By power metallurgy method, the samples of ODS-HT9 steel, which were strengthened by dispersion oxide of 0.1%~0.9% Y2O3, were prepared in order to study the effect of nano-Y2O3 on the microstructure and mechanical properties of HT9 steel. The HV, tensile strength, and elongation of the samples were ...
Application of Compressed Air Agitation in Preparation of ADUN Solution
Peng Jiancai, Li Jia, Yuan Bo, Yin Rongcai, Zhang Jie
2020, 41(2): 32-35.
Abstract(184)
Abstract:
R&D Progress of Accident-Tolerant UO2-Based Composite Fuel Pellets
Mo Huajun, Zhang Wei, Wu Lu, Luo Hao, He Wen, Pan Rongjian, Wang Zhen, Wu Xiaoyong, Wen Bang
2020, 41(2): 36-39.
Abstract(471)
Abstract:
In this paper, the research background for the advanced accident-tolerant fuel (ATF) pellets was summarized, focusing on the R&D status of accident-tolerant UO2-based composite fuel pellets at home and abroad. It is concluded that the UN, U3Si2 and ThO2 are doped phases with the most development...
Study on Ultrasonic Inspection of Baffle Bolts in Nuclear Power Plants
Wang Weiqiang, Ma Guanbing, Wang Bin, Tang Jianbang, Zeng Chenming, Xu Junlong
2020, 41(2): 40-44.
Abstract(380)
Abstract:
Baffle bolts are the critical joint parts of the internal structures in nuclear power plants, and it is necessary to perform non-destructive testing on their structural integrity in order to detect the defects such as irradiation assisted stress corrosion cracking (IASCC) which may occur during a lo...
Application of Master Curve in Reactor  Pressure Vessle Ageing
Yu Xiaohuan, Du Juan, Shao Xuejiao, Yang Yu, Liu Zhenyu, Tian Jun, Yang Lingfang
2020, 41(2): 45-48.
Abstract(307)
Abstract:
The pressure to temperature (P-T) curve is significant to ensure the vessel integrity and deal with the reactor pressure vessel(RPV) ageing. The traditional method using the material near static facture limit value (KIc) by t-RTNDT curve to plot the P-T curve cannot obtain the appropriate RTNDT for ...
Study on Functional Capability of Piping System Evaluation Criteria
Tang Feng, Li Qiang, Peng Jian, Wang Mingyu
2020, 41(2): 49-53.
Abstract(292)
Abstract:
The functional capability of piping systems is different from the pressure boundary integrity of piping system, and United States Nuclear Regulatory Commission (NRC) specified two evaluation criteria for the piping functional capability. To explore the origin and the application of functional capabi...
Buffering Effect Analysis for Secondary Supports in Reactor Vessel Internals under Assumption Accident of Core Drop
Fang Jian, Duan Yuangang, Ran Xiaobing, Ma Ruoqun
2020, 41(2): 54-58.
Abstract(249)
Abstract:
To research the buffering effect of secondary supports in reactor vessel internals under the assumption accident of core drop (core barrel broken down), a buffering effect analysis of secondary supports is performed, based on the technology of water buffering and mechanical buffering. In this paper,...
Nonlinear Dynamic Analysis of Soil-Pile Interactions of Nuclear Island with Nonlithological Foundation
Cao Liang, Shi Lin, Wu Xianmin, Huang Jianxue, Chen Bingbing, Xie Jigao, Zheng Sanlong
2020, 41(2): 59-65.
Abstract(229)
Abstract:
In the simulated water environment, the stiffness test of the shrinkage specimen of Hold Down Spring of The Reactor Internals was carried out, and compared with the analysis results of the finite element simulation, theoretical model based on small disturbance and the large disturbance follow-up mod...
Research on Stiffness Test and Calculation Model of Hold Down Spring under Simulated Water Environment
Cao Liang, Shi Lin, Wu Xianmin, Huang Jianxue, Chen Bingbing, Xie Jigao, Zheng Sanlong
2020, 41(2): 66-71.
Abstract(309)
Abstract:
In the simulated water environment, the stiffness test of the shrinkage specimen of Hold Down Spring of The Reactor Internals was carried out, and compared with the analysis results of the finite element simulation, theoretical model based on small disturbance and the large disturbance follow-up mod...
Calculation of Radionuclide Migration in Coastal Waters Based on Lagrangian Method
Li Zichao, Zhou Tao, Si Guangcheng, Qin Xuemeng
2020, 41(2): 72-77.
Abstract(265)
Abstract:
Based on the real-time meteorological data, the hydrodynamic model in the coastal waters of the nuclear power plant was established and the model reliability was verified. Then a radionuclide diffusion model in the coastal waters of the nuclear power plant was established based on the Lagrange metho...
Research of Functional Reliability Evaluation Method for Passive Systems Based on Data Mining Technology
Wang Baosheng, Tang Xiuhuan, Bao Lihong, Zhu Lei, Sun Peiwei
2020, 41(2): 78-83.
Abstract(176)
Abstract:
In order to solve the problem of multi-dimensional uncertainty parameters and small probability of functional failure, an innovative functional reliability estimation method named Data Mining Technology was presented. In the presented method, with the combination of the bootstrap response surface mo...
Study on Initial Passivation Process of Primary Loop of PWR Nuclear Power Plants
Ji Dapeng, Zhang Yeliang
2020, 41(2): 84-88.
Abstract(293)
Abstract:
The development of the passive oxide film on the primary loop during hot functional testing of PWR nuclear power plants is very important in the minimizing corrosion of the materials and corrosion product release. In this paper, based on the theoretical research and engineering practice, it is concl...
Effect of Wall Radiation on Turbulent Natural Convection Heat Transfer Characteristics in an Enclosed Cavity with Built-in Fins
Wang Ye, Zhao Xingjie, Ma Bingshan, Guan Guoxiang
2020, 41(2): 89-95.
Abstract(253)
Abstract:
In order to study the effects of wall emissivity on natural convection heat transfer characteristics of an air-filled enclosure with built-in fins, the RNG k-ε model was adopted to numerically analyze the temperature field, the flow field and the Nusselt numbers on the vertical wall of the cavity wi...
Application of Generalized Predictive Control in Reactor Core Variable Power Control
Pan Yuekai, Qian Hong, Jiang Cheng, Liu Xiaojing
2020, 41(2): 96-101.
Abstract(194)
Abstract:
Aiming at the nonlinear problem of the core power model caused by steady-state neutron density at different power levels, generalized predictive control (GPC) is applied to the core power control to realize the automatic control of the core power under variable working conditions. This paper firstly...
Reason Analysis for Unsatisfactory of Accuracy and Improvement of Accuracy of On-line Boron Meter in a Nuclear Power Plant
Zheng Junwei, Liu Yang, Deng Sheng, Ma Shu, Wang Canhui, Du Wenlong, Cui Yongle
2020, 41(2): 102-108.
Abstract(404)
Abstract:
In order to find out the reason for the unsatisfactory of measurement accuracy of the online type boron meter (BCMS) supplied by AREVA NP GmbH, the scheme to improve the BCMS measurement accuracy was studied. According to the working principle of BCMS, the factors affecting the measurement accuracy ...
Core Power Control of Liquid Molten Salt Reactor Based on Variable Universe Fuzzy-PID
Jiang Qingfeng, Zeng Wenjie, Yu Tao, Xie Jinsen, Chen Lezhi
2020, 41(2): 109-113.
Abstract(220)
Abstract:
The core system of liquid molten salt reactor is with the characteristics of non-linearity and time-varying. The initial domain of the fuzzy PID control technology cannot change following the change of error, so the control accuracy of the system is deteriorated. Therefore, the core power control st...
Research on Separation Characteristics of Two Stage Cyclone Steam Separator
Liu Yan, Ke Bingzheng, Wang Xianyuan, Yang Xuelong, Tian Ruifeng
2020, 41(2): 114-119.
Abstract(385)
Abstract:
A special two-stage whirlwind steam separator was designed based on the research of relevant domestic and foreign data, and the detailed numerical simulation research was conducted in terms of its separation performance. According to the structure of the two-stage cyclone separator, a computational ...
Failure Analysis and Design Improvement of Thin-Walled Gears for Mechanical Transmission Mechanism of Air-Lock in Nuclear Power Plants
Liu Shengyong, He Yingyong, Xie Honghu, Huang Yili, Zhang Feng, Zhang Shipeng
2020, 41(2): 120-124.
Abstract(233)
Abstract:
Research work is performed on the failure of thin-walled gears used in mechanical transmission mechanism of air-lock in nuclear power plants, based on the failure mechanism of thin-walled gears and its loading condition. The essential causes of failure of thin-walled gears founded, and they are: a. ...
Analysis of Effect of Primary Piping Diameter on Performance of Main Pump
Wang Yan, Cui Huaiming, Guo Yanlei, Mao Yuanfan, Duan Yongqiang, Li Lei, Su Xianshun
2020, 41(2): 125-129.
Abstract(280)
Abstract:
To the nuclear primary pump of PWR and its two different primary piping cold leg diameter configuration schemes, a three-dimensional model is established by combining the primary pump and the primary pipe, and the hexahedron structured mesh is used to perform the model partition and calculate the un...
Research on Crack Failure of Auxiliary Feed Water Pump Impeller Based on CFD
Li Yuanzheng, Liu Zheng, Zheng Hongen
2020, 41(2): 130-134.
Abstract(246)
Abstract:
In order to study the crack failure characteristics of the auxiliary feed pump impeller, the pressure pulsation response law of the auxiliary feed pump casing measuring point under different impeller crack lengths is explored based on CFD, and the CFD results are verified by the vibration monitoring...
Study on Modification for Auxiliary Feed Water System Temperature Beyond the Limit in Operation Technical Specification of Nuclear Power Units
Wang Shuqiang
2020, 41(2): 135-139.
Abstract(311)
Abstract:
For the unit fallback case in which the water temperature of Auxiliary Water Supply System exceeds the temperature limit in the Operation Technical Specification due to the minimum flowrate operation in Summer, the modification of installing a cooler on the line of the circulation pump for ASG tank ...
Modification of First Electrical Penetration in Domestic Nuclear Power Plants
Yi Feifan, Qian Houjun, Chen Ziming, Chen Fujie, Zeng Shu, Li Shuping, Chen Qihao
2020, 41(2): 140-144.
Abstract(303)
Abstract:
As the key equipment on the containment, the electrical penetration of nuclear power plants undertakes the important functions of various power and signal transmission inside and outside the nuclear island and ensuring the integrity of the containment pressure boundary. Through the implementation of...
Simulation Research of Ultrasonic Inspection of Primary Tube  Seat Weld in Nuclear Power Plants
Hu Chenxu
2020, 41(2): 145-149.
Abstract(235)
Abstract:
The small-size branch joint (BOSS) weld is the weak point of the primary pressure boundary in nuclear power plants, and its monitoring is critical but difficulty in the daily and in-service inspection. This paper designs and verifies the ultrasonic phased array inspection technology for BOSS welds, ...
Design Methodology for Standard Commissioning Guidelines for Native Advanced PWRs
Shang Chen, Tian Qiwei, Mao Huan, Liu Yong
2020, 41(2): 150-154.
Abstract(266)
Abstract:
As one of the basic technical guidance documents for nuclear power plant commissioning, the standard commissioning guidelines are designed to perform commissioning test with the common method for a same type of equipments and components, or a given type of test. Based on the requirements of domestic...
Analysis and Research on Key Design Parameters of Leakage Detection System for Steel Liner of Radioactive Storage Pool in Nuclear Power Plants
Chen Chuyuan, Xie Honghu, Chen Zhao, Liu Xiaohua
2020, 41(2): 155-159.
Abstract(563)
Abstract:
Leakage detection system is one of the most important parts of the steel liner for long-term radioactive storage pool. In order to confirm the key design parameters of the leakage detection system, the analysis work is performed by risk management analysis and hydrodynamics calculation methods. Base...
Diagnosis of Leakage Degree of Steam Generator Tube Based on Time Series Neural Network
Qian Hong, Jiang Cheng, Pan Yuekai, Wei Yingchen, Liu Xiaojing
2020, 41(2): 160-167.
Abstract(327) PDF(126)
Abstract:
Aiming at the leakage of the steam generator U-shaped tube, a method based on time series neural network is proposed to diagnoze the leakage degree of steam generator tube. Firstly, the leakage mechanism of the steam generator U-shaped tube of the nuclear power plant is analyzed, its mathematical mo...
Study on Production Capacity of 63Ni by HFETR Irradiation
Zhou Chunlin, Li Haitao, Zhang Jiangyun, Chen Liang, Li Ketian, Lai Lisi
2020, 41(2): 168-172.
Abstract(387)
Abstract:
To complete the production of radioisotope 63Ni based on self-reliance, the reactor physical calculation program is used to establish a balanced core model of HFETR. The process of irradiating natural nickel and high-purity 62Ni to produce 63Ni at four typical in-pile locations is simulated. The res...
Research on Interconnection Security Protection System of Nuclear Reactor Industrial Control System and Enterprise Information System
Qin Lihua, Wang Dan, Wang Daqiu
2020, 41(2): 173-177.
Abstract(232)
Abstract:
In view of the scattered and isolated security protection strategies of the nuclear reactor industrial control system and enterprise information system interconnection projects, this paper conducts a detailed analysis of the security and confidentiality risks at the management level and the technica...
Study on Pattern and Key Issues of Contactless Power Supply for Hot Cell Transfer System
Zhuo Yong, Wang Dingchao, Ye Senmao
2020, 41(2): 178-183.
Abstract(225)
Abstract:
With the analysis of the shortages of traditional power supply for hot cell transfer system, a novel contactless power supply system is proposed based on the study of magnetic coupling structure, which realizes the reliable contactless power supply for the hot cell transfer system when it moves rand...
Analysis of Accuracy and Efficiency of Two Node Method for Solving Fine Mesh SP3 Neutron Transport Equations
Zhao Wenbo, Yu Yingrui, Chai Xiaoming, Ning Zhonghao
2020, 41(2): 184-188.
Abstract(393)
Abstract:
A two node method is developed to solve the fine mesh SP3 equations. The Laplace operator on the 0th moment flux is treated by nodal method. The transverse integrated 0th moment flux is expanded to a second order polynomial, and the transverse leakage term is approximated with flat distribution. A p...
Study on Coupling Characteristics of Small Break LOCA in Advanced PWR
Jin Yuan, Jiang Xiaowei, Deng Jian, Liu Yu, Bi Shumao, Zhu Dahuan, Yang Fan
2020, 41(2): 189-192.
Abstract(359)
Abstract:
In order to understand the transient response characteristics of the passive containment cooling system, the passive core cooling system and the passive residual heat removal system after the small break LOCA in an advanced pressurized water reactor, the coupling response characteristics of the reac...
Effect of Main Feedwater Isolation Modes on Mass and Energy Release and Containment Response for MSLB
Guan Zhonghua, Qiu Zhifang, Jiang Xiaowei, Duan Yongqiang, Shen Yunhai, Fang Haoyu
2020, 41(2): 193-197.
Abstract(342)
Abstract:
Taking the 3&4 units in Qinshan Second Nuclear Power Plant as an example, the effect of two modes of feedwater isolation on the mass and energy release during a large main steam line break (MSLB) accident, by valve isolation and shutdown of the main feedwater pump, is analyzed by THEMIS code. Th...
Case Analysis of Loose Parts Alarm in Nuclear Power Plants
Jian Jie, Luo Ting, Liu Caixue, Wang Guangjin, Hu Jianrong, Yang Taibo
2020, 41(2): 198-202.
Abstract(271)
Abstract:
In view of the phenomenon that several alarms of loose parts occurred in the thermal test phase of a nuclear power plant during the overhaul, a probe was temporarily installed at a key location for field test, and the event location of the collected test data was conducted by analyzing the time diff...
A Remote Operation and Maintenance Data Management System for Nuclear Reactors Based on Integration of Big Data and Relational Data
Bai Yi, Qin Lihua, Wang Sishi
2020, 41(2): 202-206.
Abstract(335)
Abstract:
Based on the process of the nuclear power operation and maintenance, this paper overviews various operation and maintenance data in detail, analyzes the data types, data characteristics and magnitude, and then puts forward a data management framework between big data and relational data; Based on th...
Design and Application of a Remote Online Self-Checking Unit Based on Charge Signal
Li Xiang, Wang Lei, Li Hai, Zou Bohao, Fu Guoen, Deng Sheng
2020, 41(2): 207-213.
Abstract(210)
Abstract:
A remote online self-checking unit based on charge signal is designed to provide a fast and effective remote online self-checking method for the primary instrument of the Loose Parts Monitoring System (LPMS) installed in the reactor building of the nuclear power plant. The design principle and the m...
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