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2019 Vol. 40, No. 1

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General Technology Features of Reactor Core and Safety Systems Design of HPR1000
Yu Hongxing, Zhou Jinman, Leng Guijun, Deng Jian, Liu Yu, Wu Qing, Liu Wei
2019, 40(1): 1-7. doi: 10.13832/j.jnpe.2019.01.0001
Abstract(1122)
Abstract:
HPR1000 is an advanced pressurized water reactor developed by China National Nuclear Corporation (CNNC) with fully independent intellectual property rights. In this paper, the production process of HPR1000 are firstly introduced, and then the general technologyfeatures of reactor core and safety sys...
Development and Application of a New CHF Correlation for PWR Fuel Assembly
Liu Wei, Peng Shinian, Jiang Guangming, Liu Yu
2019, 40(1): 8-11. doi: 10.13832/j.jnpe.2019.01.0008
Abstract(424)
Abstract:
Based on the bundle CHF test databaseof NPIC, the minimum DNBR point method is applied in this study to develop a new CHF correlation named CF-DRW correlation for the PWRfuel assemblyto couple with the subchannel code CORTH. The results of typical accidents analysis indicate that the DNBR thermal ma...
Development and Verification of Multi-Group Constants Processing Module in NECP-Atlas
Xu Jialong, Zu Tiejun, Cao Liangzhi, Wu Hongchun
2019, 40(1): 12-17. doi: 10.13832/j.jnpe.2019.01.0012
Abstract(583)
Abstract:
Multi-group constants are the basis of the deterministic physics calculation, and the accuracy will directly affect the subsequent calculations. The methods of multi-group constants processing are developedrapidly, and the study onthe processing methods and relevant code developing have greatimporta...
Influence of Gas State Equations on Acceleration Parameter for Heat Transfer to Supercritical Carbon Dioxide Flowing in Heated Tubes
Liu Shenghui, Huang Yanping, Liu Guangxu, Wang Junfeng, Wang Jinyu
2019, 40(1): 18-22. doi: 10.13832/j.jnpe.2019.01.0018
Abstract(412)
Abstract:
Strong acceleration effect has an obvious influence on the convective heat transfer to supercritical carbon dioxide flowing in a heated tube. Acceleration parameter (A) is an important dimensionless number to represent the level of acceleration effect quantitatively. In the process of developing acc...
Transient Analysis on Unprotected Partial Flow Blockage of Hottest Fuel Assembly for A Small Natural Circulation Lead-Cooled Fast Reactor
Zhao Pengcheng, Liu Zijing, Yu Tao
2019, 40(1): 23-27. doi: 10.13832/j.jnpe.2019.01.0023
Abstract(319)
Abstract:
Corrosion of cladding and structural materials by liquid lead or LBE is one of the key issues restricting the development of lead-cold fast reactor. A primary cooling system analytical model of 100MWthsmall modular natural circulation lead-cooled fast reactor named SNCLFR-100 is established with ATH...
Modification and Verification of Critical Flow Module for LOCA Analysis Code
Wang Jie, Liu Dong, Liu Ying, Lu Tianyu, Wu Dan
2019, 40(1): 28-32. doi: 10.13832/j.jnpe.2019.01.028
Abstract(258)
Abstract:
The conservative analysis method in the analysis of loss of coolant accident(LOCA)is not conducive to improving the economic efficiency of nuclear power plants. In order to satisfy the evaluation requirements for LOCAof nuclear power plants in 10CFR50 Annex K, the model was modified to meet the eval...
Fluidelastic Instability of Rotated Triangle Tube Bundles Subject to Two-Phase Cross-Flow
Jiang Tianze, Li Pengzhou, Ma Jianzhong
2019, 40(1): 33-36. doi: 10.13832/j.jnpe.2019.01.033
Abstract(177)
Abstract:
In order to predict more accurately thecritical flow of fluidelastic instability, the motion equation of a cantilevered tube is established utilizing quasi-static fluid force coefficients of two-phase flow. After Galerkin discretization of the analytical model, the critical flow velocity of each voi...
Research on Fuel Loading Operation Scheme for Annual Refueling Core of M310 Advanced Nuclear Power Plant
He Taifeng, Liu Xinping
2019, 40(1): 37-41. doi: 10.13832/j.jnpe.2019.01.0037
Abstract(598)
Abstract:
This paper discusses the difficulties of the loading operation process forthe annual refueling core of M310 improved nuclear power unit, and studies the arrangement of the annual refueling core, the deformation form of the fuel assembly and the loading measures of the M310 improved nuclear power uni...
Feasibility Study on Conceptual Design of Dual Fluid Fast Reactor
He Xun, Zeng Chang, Yu Xiaoquan, Du Zhuoqi, Rafael Macián-Juan
2019, 40(1): 42-47. doi: 10.13832/j.jnpe.2019.01.0042
Abstract(335)
Abstract:
The development of DFFR stays in the phase of conceptual design, which leads to the main discussion of this work that is to quantitatively evaluate the feasibility of this reactor type and the effects of those parameters on the reactor physical behavior. The evaluation includes two parts: the critic...
Determination for 235U Enrichments of Same Geometry and Mass Uranium Components by BP Neural Network
Ren Lixue, Liu Zhigui, Zhou Zhiru
2019, 40(1): 48-50. doi: 10.13832/j.jnpe.2019.01.0048
Abstract(217)
Abstract:
To identify metal uranium components with same geometry and mass but different enrichments, 252Cf source noise analysis was used to gain the neutron time correlation coincidence measurement. Based on the analysis and processing of neutron time correlation coincidence measurement, the characteristic ...
Research on Preparation Method for Zr-4 Tubes with Different Hydride Orientation
Chen Boquan, Peng Qian, Zeng Zihan, Zhao Suqiong, Hong Xiaofeng, Qiu Shaoyu, Xu Chunrong
2019, 40(1): 51-55. doi: 10.13832/j.jnpe.2019.01.0051
Abstract(236)
Abstract:
Zr-4 tubes with 140±20ppm(1 ppm=1 μg/g)and 260±20ppm hydrogen were prepared by using electrolysis hydrogenating method,and these tubes were further undergone the effect of hydride stress reorientation through loading high pressure gas. Finally, Zr-4 tubes with different hydride orientation were rece...
Study on Fabrication and Microstructural Analysis of U3Si2 Fuel Pellets
Zhang Xiang, Liu Guiliang, Liu Yunming, Xiao Hongxing, Liu Yu, Chen Rong, Zhang Ruiqian
2019, 40(1): 56-59. doi: 10.13832/j.jnpe.2019.01.0056
Abstract(766)
Abstract:
Uranium silicide is formed from ingot of uranium and silicon in near stoichiometric quantities by arc melting. And then uranium silicide pellets wereproduced by conventional powder metallurgy. The effect ofpellet compression molding and sintering ondensity and the microstructure of U3Si2 pellets wer...
Effect of Hydride Orientation on Tensile and Bursting Properties of Zr-4 Cladding Tubes at Room Temperature
Chen Boquan, Peng Qian, Hong Xiaofeng, Liu Ranchao, Qiu Shaoyu, Xie Huaiying, Chen Le
2019, 40(1): 60-64. doi: 10.13832/j.jnpe.2019.01.0060
Abstract(524)
Abstract:
The effect of hydride orientation on mechanical properties of Zr-4 tubes with hydrogen contents with 140±20μg/g and 260±20μg/g was investigated by tensile and bursting tests at room temperature. The results showed that with the two studied hydrogen contents, thehydride orientation had little influen...
Tritium Permeation in RAFM Steel
Lu Guangda, Xiang Xin, Bao Jingchun, Fan Dongjun, Zhang Guikai, Chen Changan, Tang Tao
2019, 40(1): 65-68. doi: 10.13832/j.jnpe.2019.01.0065
Abstract(243)
Abstract:
The tritium permeability of CLAM steel, one of the low activated ferrite/martensite steels (RAFM steels)made in China, have been experimentally measured by means of the gas evolution permeation techniqueover the temperature range of 573-823K. The resultant permeability FTis 2.57×10-8exp(-38639/RT),t...
Research on UF4 Producing Techniques by Fluoridation of U3Si2 Powder
Zhang Fan, Yu Xiaochuang, Li Tao, Guo Bolong
2019, 40(1): 69-73. doi: 10.13832/j.jnpe.2019.01.0069
Abstract(261)
Abstract:
There are many kinds of unqualified uranium containing materials with large stock. In order to improve the utilization rate of uranium and meet the stable supply of materials needed for fuel element production, uranium recycling is needed. It is introduced that U3Si2powder can be converted into uran...
Study on Process and Properties of Pulse Laser Prepared Cr Coating for Accident Tolerant Fuel Claddings
Li Rui, Liu Tong
2019, 40(1): 74-77. doi: 10.13832/j.jnpe.2019.01.0074
Abstract(477)
Abstract:
This paper introduces the latest ATF cladding achievementsof China General Nuclear Power Corporation (CGN). The Cr coating of Zircon with different thickness was prepared under different power by pulse laser cladding technique. The results obtained so far show that Cr coating can achieve good high t...
Design and Numerical Research of Thermal Insulation Water Layer for Built-in Pressurizer
Zeng Chang, Sui Haiming, Ren Yun, Zhong Fajie
2019, 40(1): 78-81. doi: 10.13832/j.jnpe.2019.01.0078
Abstract(287)
Abstract:
A thermal insulation water layer is designed for the built-in pressurizer of ACP100+ small model reactor. The flow and heat transfer characteristicsof heat insulation water layer are researched using numerical method, and the temperature and velocity distributing during power operation steady condit...
Numerical Analysis of Dynamic Response for SG LOCA Shaking
Huang Qian, Yu Xiaofei, Qi Huanhuan, Feng Zhipeng, Jiang Naibin, Song Haiyang
2019, 40(1): 82-86. doi: 10.13832/j.jnpe.2019.01.0082
Abstract(231)
Abstract:
Through reasonable simplification and equivalencefinish, a detailed nonlinear finite element model of steam generator (SG) of a domestic 3rd generation nuclear power plant (NPP) is established. This model is then connected with the reactor coolant loop (RCL) to carry out the analysisofdynamic respon...
Research of Operating Behavior and Response Time in Digital Control Room of Nuclear Power Plants
Li Linfeng, Xiang Xiaohan
2019, 40(1): 87-90. doi: 10.13832/j.jnpe.2019.01.0087
Abstract(649)
Abstract:
In this paper, the operator simulator retraining in a certain nuclear power plant with a digital control room is to be carried out a field observation, in order to collect image data of operating behavior and response time in the digital operating platform. According to the applied behavior analysis...
Analysis of Emergency Crew Behavior in the Process of Severe Accident Mitigation in Nuclear Power Plants
Chen Shuai, Zhang Li, Qing Tao, Li Linfeng, Liu Zhaopeng, Niu Maolong
2019, 40(1): 91-96. doi: 10.13832/j.jnpe.2019.01.0091
Abstract(295)
Abstract:
In order to analyzethe behavior characteristics of the nuclear power plant crew when dealing with severe accidents, focusing on the study for the particularity of Severe Accident Management Guideline,combined with field investigation and interviews with operator and emergency technical support perso...
Analysis of R Bank Frequent Action Problem in Yangjiang Nuclear Power Plant
Xiang Hongyi, Liu yang, Huang Zhenguang, Chen Jiancai, Chen Kailin
2019, 40(1): 97-100. doi: 10.13832/j.jnpe.2019.01.0097
Abstract(223)
Abstract:
In the 2ndand 3rd nuclear fuel cyclesof Unit1,Unit2 and Unit3inYangjiang Nuclear Power Plant, , R bank acts frequently,seriously affecting the safety with operation of the unit.In this paper, the logic control principle of R bank and the loading of core are analyzed, and the transfer function of fir...
Research and Application of the Blowdown Cave Hydraulic Flushing Device of the Horizontal Steam Generator
Yan Weifeng, Liu Jianmin
2019, 40(1): 101-104. doi: 10.13832/j.jnpe.2019.01.0101
Abstract(208)
Abstract:
In order to clean up corrosion depositsin theblowdown cave ofsecondary sideof steam generators in Unit 1&2 of Tianwan nuclear power station and reduce its corrosion risk to base metal of shell andweld joints, a hydraulic flushing device was developed and applied during the outages.Through hydrau...
Analysis and Countermeasures of Vibration for Variable Frequency Pump in Nuclear Power Plants
Dong Baoze
2019, 40(1): 105-109. doi: 10.13832/j.jnpe.2019.01.0105
Abstract(219)
Abstract:
During the startup process of a nuclear power plant, a variable frequency pump has a large vibration fault in a frequency range. The vibration is not conducive to the long-term operation of the pump, so a knocking test is carried out to get the natural frequency of the pump. It is determined by the ...
Research and Design of Rod Control Cabinet in Nuclear Power Plants Based on Digital Control
Xu Mingzhou, Huang Kedong, Zheng Gao, Li Guoyong, Li Mengshu, He Jiaji
2019, 40(1): 110-115. doi: 10.13832/j.jnpe.2019.01.0110
Abstract(334)
Abstract:
There are disadvantages such as poor applicability, slow dynamic response of load output and poor anti-interference ability of the rod control power supply cabinet in operation. This paper redesigns a new type of power cabinet based on programmable logic controller (PLC) and digital signal processin...
Research on Calculations of Radioactive Source Terms for PWR Nuclear Power Plants
Xu Yanfeng, Zhang Pengfei
2019, 40(1): 116-119. doi: 10.13832/j.jnpe.2019.01.0116
Abstract(655)
Abstract:
In this paper, the method to calculate the radioactive source terms released to the environment is provided based on the analysis results of samples in the containment atmosphere during an accident at a PWR Nuclear Power Plant, relevant factors are discussed, and the validity is verified through the...
Numerical Research on Source Inversion for Nuclear Accidents Based on Variational Data Assimilation Coping with Truncated Total Least Squares
Liu Yun, Liu Xinjian, Li Hong, Fang Sheng, Mao Yawei, Qu Jingyuan
2019, 40(1): 120-125. doi: 10.13832/j.jnpe.2019.01.0120
Abstract(313)
Abstract:
In a nuclear accident, release source term is the key issue of nuclear emergency and consequences assessment. Source inversion for nuclear accidents is a way to estimate the source term by using the environmental monitoring data during the accident. Since it does not rely on the reactor state parame...
Study on Impact of Leakage of Toxic and Hazardous Gases on Habitability of Main Control Room Based on ALOHA
Li Hui, Li Chaofeng, Shi Yanming, Xiong Min
2019, 40(1): 126-130. doi: 10.13832/j.jnpe.2019.01.0126
Abstract(193)
Abstract:
Basedon a nuclear power plant in Chinaand the assess principle of the Regulatory Guide 1.78-Evaluating the Habitability of aNuclear Power Plant Control Room during aPostulated Hazardous Chemical Release, the U.S. nuclear safety guide, we collected and screened the chemicals used in this project, and...
Study on Dynamic Adsorption of Gaseous Iodine by Silver Loaded Mordenite and Alumina
Xiong Wei, Cao Qi, Wang Haijun, Chen Yunming, Wu Wangsuo, Zhang Jinsong
2019, 40(1): 131-134. doi: 10.13832/j.jnpe.2019.01.0131
Abstract(262)
Abstract:
A dynamic adsorption device was designed for high humidity and high nitrogen oxide iodine gases produced by nuclear facilities. Silver-loaded mordenite and silver-loaded alumina were prepared for adsorbing gaseous iodine. The adsorption properties of silver-loaded mordenite and silver-loaded alumina...
Development of Nuclear Reactor Design Software Verification Database System
Liu Ying, Feng Bo, Cao Guohai, Tang Lei, Feng Jintao, Lu Jiachuan, Yu Yang, Zhou Yueshan, Qiang Shenglong
2019, 40(1): 135-139. doi: 10.13832/j.jnpe.2019.01.0135
Abstract(140)
Abstract:
The nuclear reactor design software verification database system was developed in this paper, aiming at the actual demands of professional data during software verification from many majors, such as reactor core physics, thermal-hydraulic analysis, fuel design, etc. Logic structure and technical fra...
Analysis of Background Noise Power Spectrum for Steam Generator of Sodium Cooled Fast Reactor
Cao Yunqi, Liu Guijuan, Liu Zhiguo
2019, 40(1): 140-143. doi: 10.13832/j.jnpe.2019.01.0140
Abstract(222)
Abstract:
In order to understand the variation of fluid operation and internal composition in the steam generator of sodium-cooled fast reactor, the AR model of modern spectrum estimation and the periodic graph method of classical spectrum estimation, Welch improved periodic graph method and BT method are int...
Methods to Determine Intensity of Historical Earthquake in Nuclear Power Plant Sites
Wang Ji, Zhang Yushan, Yan Jingru, Zhang Yujie
2019, 40(1): 144-146. doi: 10.13832/j.jnpe.2019.01.0144
Abstract(427)
Abstract:
The three methods for determining the influenceintensity of the historical earthquake in nuclear power plant sitesare the method for extrapolation of the seismic isosematics,the methods of judging data of earthquake damage investigation in ancient buildings, and themethod of investigation and judgme...
Study on Transient Performance in Loss of Coolant Accident for AP1000 SFP
Duan Yongqiang, He Xun, Jing Futing, Cai Zhiyun, Yu Xiaoquan
2019, 40(1): 147-151. doi: 10.13832/j.jnpe.2019.01.0147
Abstract(274)
Abstract:
The coupled mathematical thermal equilibrium modelfor main equipment in the spent fuel pool (SFP) is established and the transientchange of the temperatureofSFP water in various loss of coolantaccidents is studied based on AP1000 power plant. The results show that the fuel rods are exposed after 24h...
Comparative Study of CHF Correlations in Upflow Boiling Vertical Round Tube under High Pressure
Liu Wei, Peng Shinian, Jiang Guangming, Liu Yu, Shen Caifen, Shan Jianqiang
2019, 40(1): 152-155. doi: 10.13832/j.jnpe.2019.01.0152
Abstract(248)
Abstract:
Based on the experiment database of upflow boiling in the vertical round tube from 15MPa to critical pressureof water, the Katto, Bowring, Hall-Mudawar, Alekseev correlation and LUT-2006 are comparatively studied. With the error analysis of the CHF correlations to the experiment database, the applic...
Research on Failure Mechanism of M3 Fuel under Steady-State Operation Conditions
Li Yuanming, Tang Changbing, Yu Hongxing, Xin Yong, Chen Ping, Zhou Yi
2019, 40(1): 156-161. doi: 10.13832/j.jnpe.2019.01.0156
Abstract(182)
Abstract:
In orderto optimize the designof M3 fuel and further improve its reliability in LWR environment, it is necessary to research its failure mechanism under steady-state operation conditions. Based on the ABAQUSsoftware, a 3D numerical simulation analysis method for the irradiation-thermal-mechanical co...
Study on Characteristics of Core Barrel Shell Mode Vibration Based on Neutron Noise Analysis
Li Yun, Liu Caixue, Luo Ting, Yang Taibo
2019, 40(1): 162-166. doi: 10.13832/j.jnpe.2019.01.0162
Abstract(189)
Abstract:
The vibration ofthereactor core barrel reflects the vibration condition and equipment stability of the core barrel and corresponding reactor internals. This paper mainly focuseson the vibration characteristics of the core barrel shell mode with neutron noise technique and time-frequency signal analy...
Analysis for Abnormal Shaft Vibration of Main Coolant Pump in Nuclear Power Plants
Li Zhen, Yuan Shaobo
2019, 40(1): 167-171. doi: 10.13832/j.jnpe.2019.01.0167
Abstract(298)
Abstract:
To solve the shaft vibration alarm problem of the main coolant pump in a nuclear power plant, the reason diagnosis and field verification are carried out. The methods of comparison analysis, spectrum analysis and orbit analysishave been applied to investigate the abnormal shaft vibration.The analysi...
Research on Current Monitoring and Fault Diagnosis Technology for Control Rod Drive Mechanism
Zeng Jie, Peng Cuiyun, He Pan, Liu Caixue
2019, 40(1): 172-175. doi: 10.13832/j.jnpe.2019.01.0172
Abstract(413)
Abstract:
The control rod drive mechanism(CRDM) is the actuator of the reactor control and nuclear safety protection system. Animportant measure to prevent the occurrence of control rod stuck, sliding rod and driving failure in the reactoris to effectively monitor the operation status of the CRDM. Based on th...
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