核动力工程

Calculation of Higher Eigenmodes of Neutron Transport/Diffusion Forward and Adjoint Equations Using IRAM Algorithm Based on Domain Decomposition

Wu Wenbin, Luo Qi, Yu Yingrui, Li Qing, YAo Dong

2017, 38(S2): 1-6. doi: 10.13832/j.jnpe.2017.S2.0001

Abstract(19) PDF(0)

Abstract:
For the higher eigenmodes of neutron transport/diffusion forward and adjoint equations, there are various application perspectives for engineering purposes, such as core power distribution reconstruction, stability analysis, and uncertainty and sensitivity analysis. In this paper, the higher eigenmo...

Preliminary Numerical Simulation of Fuel Assembly Deformation under Non-Homogeneous Irradiation Environment

Su Min, LI Yuanming, Chen Ping, Wang Haoyu, Pu Cengping, QI Min, Zhu Fawen

2017, 38(S2): 7-10. doi: 10.13832/j.jnpe.2017.S2.0007

Abstract(16) PDF(0)

Abstract:
Considering non-homogeneous fast neutron environment and material irradiation effects, numerical simulation of typical 17×17 fuel assembly overall deformation is preliminary realized based on assumptions and simplification. Under the inputs of large fast neutron fluence and fast neutron fluence grad...

Improvement in Neutron Transport of KYCORE Code

Tang Xiao, LI Qing, Chai Xiaoming, Tu Xiaolan, Wang Kan

2017, 38(S2): 11-15. doi: 10.13832/j.jnpe.2017.S2.0011

Abstract(24) PDF(0)

Abstract:
KYCORE is a 3 D nuclear reactor numerical calculation software and it is developed from KYLIN-2, a 2 D assembly calculation software developed in Nuclear Power Institute of China. The neutron transport part uses 2 D MOC and 1 D SN coupling to realize high precision through direct angular flux coupli...

Numerical Research on Irradiation-Thermal-Mechanical Coupling Behavior of FCM Fuel

Tang Changbing, LI Wenjie, Chen Ping, LI Yuanming, ZhOu Yi, LI Wei

2017, 38(S2): 16-19. doi: 10.13832/j.jnpe.2017.S2.0016

Abstract(23) PDF(3)

Abstract:
User defined subroutines were coded under the calculation frame of ABAQUS software, and then, the irradiation-thermal-mechanical coupling behavior simulation method of fully ceramic micro-capsuled（FCM） fuel was preliminary established. With this simulation method, the in-pile behaviors of TRISO part...

Undirected Graph Partitioning Method of Matrix Algorithm in Reactor Sub-Channel Analysis

Ming Pingzhou, Pan Junjie, an Ping, Lu Wei, LIu Dong, Yu Hongxing, Sun Yufa

2017, 38(S2): 20-24. doi: 10.13832/j.jnpe.2017.S2.0020

Abstract(20) PDF(0)

Abstract:
In scale of fuel element level in the reactor core, the enthalpy conservation equation and momentum conservation equation are solved by using the structured mesh manner of according matrix algorithm in the sub-channel analysis code named CORTH. At present, parallel computing is introduced to enhance...

CFD Simulation of Subcooled Boiling in a Full-Size 5×5 Rod Bundle with Spacer Grids

LI Quan, Avramova M, LIu Yanghua, Zheng Meiyin, Zhao Yanli, Chen Jie, Jiao Yongjun, Yu Junchong

2017, 38(S2): 25-28. doi: 10.13832/j.jnpe.2017.S2.0025

Abstract(22) PDF(0)

Abstract:
In this paper, two-phase CFD approach is used to simulate the subcooled boiling flow in PSBT full-size rod bundle with spacer grids. The calculated surface averaged void fraction in the central four subchannels shows good agreement with the experimental data at high void fraction conditions, while h...

Numerical Simulation Study on Resistance Characteristics of Top Nozzle in Fuel Assembly Based on CFD

Wei Zonglan, Du Sijia, Wang Xiaoyu, Wu Guanghao, Liu Songtao, Zhang Yu

2017, 38(S2): 29-33. doi: 10.13832/j.jnpe.2017.S2.0029

Abstract(22) PDF(0)

Abstract:
In this paper, numerical simulation study is conducted for the flow of coolant in the top nozzle of the fuel assembly based on CFD methodology and the general simulation settings have been proposed. Comparison between the results of measured coefficient in the experiment and CFD simulation validated...

Research in U₃Si₂-Al Fuel Swelling Characteristics

Guo Zixuan, Li Yuanming, Lu Liangliang, Su Min, Xin Yong

2017, 38(S2): 34-37. doi: 10.13832/j.jnpe.2017.S2.0034

Abstract(27) PDF(1)

Abstract:
Based on diffusion dynamics, U₃Si₂-Al interdiffusion layer growth model and fuel swelling model under irradiation condition were established. With fuel irradiation test data for China ENgineering TEst Reactor（CENTER）, the validity and applicability of the models all above were demonstrated. The resu...

Study on Flow Mixing inside Rod Bundle Based on Image Processing Algorithm

Wang Xiaoyu, Tan Sichao, Du Sijia, Zhang Yu, Wei Zonglan, LIu Yu, Deng Jian

2017, 38(S2): 38-41. doi: 10.13832/j.jnpe.2017.S2.0038

Abstract(21) PDF(0)

Abstract:
Flow characteristics of the coolant inside the nuclear fuel rod bundle is an important research topic for reactor thermal-hydraulic safety analysis. Visualization experiment results of the rod bundle with spacer grid were studied in this paper, and fluid mixing inside the rod bundle was analyzed qua...

Sensitivity Analysis of Key Parameters for Dynamical Analysis of Reactor Coolant System

Xiong Furui, YE Xianhui

2017, 38(S2): 42-45. doi: 10.13832/j.jnpe.2017.S2.0042

Abstract(21) PDF(1)

Abstract:
Dynamical analysis of reactor coolant system（RCS） under extreme accidents is a key technical approach for nuclear power plant safety assessment. Quantitative examination of the sensitivity of key RCS structural parameters against system dynamical responses is a crucial aspect for the reliable evalua...

An Investigation of Genetic Algorithm Based Mechanical Property Optimization Method for Nuclear Piping

Bai Xiaoming, Zheng Liangang, Wang Xinjun, Lu Xifeng, Zhang Rui, Yangjie

2017, 38(S2): 46-49. doi: 10.13832/j.jnpe.2017.S2.0046

Abstract(22) PDF(0)

Abstract:
In the nuclear steam supply system, the magnitude of nuclear piping is large and their layout are complicated. In order to keep the nuclear piping satisfing the design requirements, the optimization of the location and function of supports on the piping is significant during the design. The traditio...

Analysis of Dynamic Characteristics of Thrust Bearing for Nuclear Power Plant RCP during Loss of Power Coastdown

Deng Xiao, Wang Yan, Deng Liping, Mao Yuanfan, Zhou Ning, LIu Jia

2017, 38(S2): 50-54. doi: 10.13832/j.jnpe.2017.S2.0050

Abstract(24) PDF(1)

Abstract:
The dynamic characteristics of the thrust bearing for one nuclear power plant reactor coolant pump（RCP） during loss of power coastdown has been simulated and analyzed. Firstly the axial force of the RCP rotor has been derived. Then a mathematical model for the thrust bearing has been established bas...

Numerical Simulation of Thermal Striping in Pressurizer Surge Line

Cao Simin, Huang Wei, Yang Ming

2017, 38(S2): 55-59. doi: 10.13832/j.jnpe.2017.S2.0055

Abstract(18) PDF(0)

Abstract:
This paper studies the thermal striping in the pressurizer surge line to find the reason causing the phenomenon and acquire the temperature oscillation frequency and amplitude during reactor heat up processes. Numerical studies on the thermal striping were carried out by using dynamic Smagorinsky ed...

Study on Dynamic Simulation of Rod Dropping Behavior under Ocean Conditions

Zhu Zihao, Peng Hang, Luo Ying, LIu Jia, Du Hua

2017, 38(S2): 60-63. doi: 10.13832/j.jnpe.2017.S2.0060

Abstract(17) PDF(0)

Abstract:
The reactor control rod drive line is an important part for the reactor safety control function. It consists of the control rod drive mechanism, the control rod assembly and its guiding system, which is the only structural equipment with relative movement in the heap. Under the ocean conditions, the...

Impact-Buffer Process Analysis Method for Control Rod Drive Line Buffer Structure

Yan Dapeng, Du Hua, Liu Jia, Duan Chunhui, Zhu Zihao

2017, 38(S2): 64-69. doi: 10.13832/j.jnpe.2017.S2.0064

Abstract(24) PDF(1)

Abstract:
The paper discusses the application of continuous contact force model in the process of collision between a typical buffer structure and bearing components. The differences between compressible fluid hydraulic buffer model and incompressible fluid hydraulic buffer model are compared. Combining the c...

Study on Sealing Behavior of Laterally One Side Restrained C-Ring under Internal Pressure by Numerical Simulation

Dong Yuanyuan, Luo Ying, YIN Qiwei, Yang Zhihai, Wang Xuxin

2017, 38(S2): 70-74. doi: 10.13832/j.jnpe.2017.S2.0070

Abstract(14) PDF(0)

Abstract:
This paper established a 3 D numerical simulation method to study the laterally one side restrained C-ring under internal pressure. In this paper, it found that with the internal pressure forcing and sealing groove squeezing, C-ring would generate additional plastic deformation, which would decrease...

Dynamic Simulation Study on Pulse-Campbell Join Section of Fission Chamber

Luo Tingfang, Zhu Hongliang, GAo Zhiyu, BAo Chao, LIu Lixin

2017, 38(S2): 75-78. doi: 10.13832/j.jnpe.2017.S2.0075

Abstract(16) PDF(0)

Abstract:
Fission chamber is with the advantages of wide measuring range and high immunity on Gama ray. But there is a difficult problem of the convergence when the pulse counting method and Campbell method are introduced in the measurement. Tests conducted based on the reactor are with high cost and limited ...

Analysis of Control Rod Dropping and Buffering Behavior of Supercritical Water-Cooled Reactor Based on Dynamic Grid Technology

Xiao Cong, Luo Ying, Zhang Hongliang, LIu Xiao, Du Hua, HuanG Kedong, MO Chao

2017, 38(S2): 79-83. doi: 10.13832/j.jnpe.2017.S2.0079

Abstract(28) PDF(0)

Abstract:
Dynamic simulation analysis of the control rod dropping behavior of the supercritical water-cooled reactor（SCWR） is carried out based on the dynamic mesh technology of computational fluid dynamics（CFD） in this paper. And the characteristic parameters and characteristic curves of the control rod drop...

Device and Method for Nuclear Auxiliary Pump New Cavitation Test

Wan Yi, Chen Zhihui, LI Yi, Xiao Kunjian, Lu Xin, He Ronghui, LI Chunmei

2017, 38(S2): 84-86. doi: 10.13832/j.jnpe.2017.S2.0084

Abstract(21) PDF(0)

Abstract:
The cavitation test device and method for the nuclear auxiliary pump is designed, which is a closed type of using water ring vacuum device and valve micro degree for the cavitation test. In the process of test, there is no need to switch the water ring vacuum device and valve, only the startup and t...

Study on Effect of Transition Section on Safety Injection and Corresponding Mitigation Measures in Floating Nuclear Power Plants

HAo Chengming, Wan Yi, SuN Guanyu, ZhAo Jing, SuN Yan, Wang Yu, LI Chunmei, LIang Tiebo, Yan Siwei

2017, 38(S2): 87-92. doi: 10.13832/j.jnpe.2017.S2.0087

Abstract(30) PDF(0)

Abstract:
In this paper, floating nuclear power plant is studied and RELAP5 is used to analyze the effect of water-seal-structure on the safety injection when occurring the lose of coolant accident with a particular broken size, and investigate the influence pattern of water-seal-structure on the safety injec...

Analysis and Improvement of Phase Differential Protection Malfunction of Main Transformer in Nuclear Power Units

Chen Jiqing

2017, 38(S2): 93-96. doi: 10.13832/j.jnpe.2017.S2.0093

Abstract(19) PDF(0)

Abstract:
This paper elaborates the principle of the phase differential protection, analyzing the failure according to an event of the phase differential protection malfunction of the transformer. It proposes the improvement in the type of current transformer and the setting, to avoid the simple faults and pr...

Reasons and Solutions for Temperature Difference between Two Sides of ADG Deaerator during Start-up

Chen Jiaqing

2017, 38(S2): 97-99. doi: 10.13832/j.jnpe.2017.S2.0097

Abstract(24) PDF(0)

Abstract:
In the hot commissioning of Fangjiashan nuclear power project, a relatively large temperature difference was found between the two ends of the deaerator in the feedwater deaerator system（ADG）. Displays in the main control room show that the temperature difference was nearly 40 degrees. After a detai...

Analysis and Treatment of Weld Defects in Negative Pressure Cavity Valve of Main Pipeline in Nuclear Reactor

Shao Zhen, Cheng Xiaowen, Le Yu

2017, 38(S2): 100-103. doi: 10.13832/j.jnpe.2017.S2.0100

Abstract(21) PDF(0)

Abstract:
Negative pressure cavity valve for coolant flow rate in the primary loop main pipeline of nuclear power plants connects with the main pipeline by the way of welding. In this paper, the treatment of weld defect before a negative pressure cavity valve for 30 MW unit in Qinshan Nnuclear Power Plant has...

Discussion of Nuclear Hydrogen Ignition Equipment Selection

Dong Yuling

2017, 38(S2): 104-109. doi: 10.13832/j.jnpe.2017.S2.0104

Abstract(24) PDF(0)

Abstract:
In order to eliminate concentration hydrogen in the containment under the severe accidents of nuclear power plants, it is necessary to add Hydrogen Ignition Equipment. The paper analyzes the main theory of the hydrogen igniter and passive autocatalytic recombiner which are used mostly, and how to se...

Influence Analysis of SVDU Fault on Nuclear Power Plant Control Model and Corresponding Technical Solutions

Du Congbo, Yuan Shangcao

2017, 38(S2): 110-114. doi: 10.13832/j.jnpe.2017.S2.0110

Abstract(32) PDF(0)

Abstract:
This paper introduces the fault analysis of FJS NPP SVDU of the unit control mode, analyzes the reasons and gives corresponding technical solutions. After the implementation of the technical program, this paper analyzes from several aspects: the elimination of 5 groups of KIC/BUP switch logic interl...

Disposal of Low-Polluting Metal Wastes in Decommissioning of Nuclear Power Plants

Fan Kai, HuanG Wentao, Wang Yongchao, JIang Shenghan

2017, 38(S2): 115-118. doi: 10.13832/j.jnpe.2017.S2.0115

Abstract(22) PDF(0)

Abstract:
Nuclear power plant decommissioning will produce large amounts of metal wastes, and the disposal of the parts with radioactive contamination should follow the appropriate classification and processing guidelines. Based on the analysis of international and domestic standards, this paper puts forward ...

Research on Double Stage Vibration Isolation System of Vibratory Machine for Reactor Coolant System Based on Four-Pole Parameter Method

JIang Shenghan, Zhang Kun, Fan Kai, Li Zhibin, Li Pengzhou, Wang Yongchao

2017, 38(S2): 119-123. doi: 10.13832/j.jnpe.2017.S2.0119

Abstract(29) PDF(0)

Abstract:
The four-pole parameter model of the isolation system was established to study the effect of the main parameters, such as middle mass and stiffness of the isolator, on the vibration isolation of the system by using the four-pole parameter method, and the principle which could be referenced in the de...

Analysis and Treatment of Shell Reduction of Moisture Separator and Reheater for Nuclear Power Stations

LI Hongjun, Wang Jian, Yang Biao, YIN Kaiju, Shi Jingfeng, Zhou Yu, Peng Yuejun

2017, 38(S2): 124-127. doi: 10.13832/j.jnpe.2017.S2.0124

Abstract(24) PDF(0)

Abstract:
After long-term operation, the thickness of the shell of the 1# Moisture Separator and Reheater in CNNO Qinshan PhaseⅠPower Plant has been reduced. The analysis reveals that the flow accelerated corrosion is the root cause. If the corrosion is allowed to continue, the equipment strength will be furt...

Research on Intergranular Corrosion of Alloy 690 Used in SG Tubes

Lin Zhenxia, Dang Ying, Xu Qi, Chen Yong

2017, 38(S2): 128-130. doi: 10.13832/j.jnpe.2017.S2.0128

Abstract(17) PDF(0)

Abstract:
According to the standard（GB/T 15260-1994）, the experiments of intergranular corrosion of homemade and imported Alloy 690 used in SG tubes are conducted in boiling HNO₃ solutions and boiling H₂SO₄-Fe₂（SO₄）₃ solutions. The intergranular corrosion rate and microstructure of tested specimens are obtain...

Corrosion Impact of Chilled Water Leaking into RCW System and Countermeasures

Lu Yeting, YOu Zhaojin, Shen Yafang

2017, 38(S2): 131-135. doi: 10.13832/j.jnpe.2017.S2.0131

Abstract(21) PDF(1)

Abstract:
The circulating cooling water system（hereinafter referred to as RCW system） and chilled water system using inhibitor is different in CNNO NPP3. The chemical analysis showed that the corrosion inhibitor by nitrite is frozen water leaking into the hydrazine/lithium hydroxide as RCW inhibitors will mak...

Application of NASPIC in Fangjiashan Nuclear Power Plant

Ma Bin, Wang Xi, Pan Donghui

2017, 38(S2): 136-139. doi: 10.13832/j.jnpe.2017.S2.0136

Abstract(20) PDF(0)

Abstract:
Fangjiashan nuclear power plant environmental radiation and meteorological monitoring system（KRS） signals from Fangjiashan off-site emergency center building. There are security risks of network attacks, affectting the stable operation of the whole unit DCS. To solve potential risk of information se...

Study on Core Characteristics of Thorium-Fueled CANDU Reactor

Meng Zhiliang, Fan Shen, Wu Tianyuan, Chen Mingjun, Zhang Zhenhua

2017, 38(S2): 140-142. doi: 10.13832/j.jnpe.2017.S2.0140

Abstract(23) PDF(0)

Abstract:
All the operating CANDU heavy water reactors are using natural uranium as the fuel, however, owing to the unique design features, the heavy water reactor actually is with high fuel flexibility, low-enriched uranium, anduranium and thorium to be reprocessed as well. The paper intends to study the pot...

Physics Tests to Verify Performance of Vanadium Detectors of Qinshan Pressurized Heavy Water Reactor after First Replacement

Shi Xingjin

2017, 38(S2): 143-145. doi: 10.13832/j.jnpe.2017.S2.0143

Abstract(25) PDF(0)

Abstract:
With the increasing of neutron irradiation time, the sensitivity of the vanadium detectors will reduce and even lose efficacy. Therefore, the vanadium detectors need to be integral replaced after operating a certain period of time. This paper mainly discusses and analyzes the design and implementati...

Analysis and Confiring of Acceptance Criteria in Diverse Actuation System Signals Design for Nuclear Power Plants

Tian Haowen, Guan Zhonghua, Xiao Peng

2017, 38(S2): 146-148. doi: 10.13832/j.jnpe.2017.S2.0146

Abstract(27) PDF(0)

Abstract:
This paper introduces the design flow and method of diverse actuation system（DAS） signals, and discusses the process of analyzing and confirming the acceptance criteria for fixing diverse actuation system protecting signal set. The method is clarified, and the acceptance criteria is confirmed for di...

Study on DCS Operation and Maintenance Strategy of Nuclear Power Stations

Tian Lu

2017, 38(S2): 149-151. doi: 10.13832/j.jnpe.2017.S2.0149

Abstract(17) PDF(0)

Abstract:
This paper analyzes the key impacts that DCS system brings to the nuclear power plant operations with real cases, and based on these analyses, it proposes the requirement that non-safety DCS systems could also apply Single-Failure criteria in nuclear power plants. In the meantime, this paper propose...

Study on Forming Technology of Anti-Water Erosion Shields Made of Stellite Alloys

Wang Miaomiao, Zhang Xingtian, Wang Jun, Geng Jianqiao, Yu Weiwei, Chen Mingya

2017, 38(S2): 152-154. doi: 10.13832/j.jnpe.2017.S2.0152

Abstract(19) PDF(0)

Abstract:
The molding process, microstructure and structural mechanics of the Stellite sheet are discussed, and the potential cause of cracking is shown in this paper. The surface stress of the Stellite alloys is changed after the mechanical polish, and the size of the grain in the surface and internal of the...

WCAP Methodology Related to Chemical Effect of Containment Sump Strainer in PWR

Tang Ming, Wang Tao, Xia Xiaojiao, Jia Xiaohong, Xing Dianchuan, LI Yong

2017, 38(S2): 155-159. doi: 10.13832/j.jnpe.2017.S2.0155

Abstract(33) PDF(0)

Abstract:
The block of containment sump strainer is one of the primary safety concerns. A regulatory guide of RG1.82 WATER SOURCES FOR LONG-TERM RECIRCULATION COOLING FOLLOWING A LOSS-OF-COOLANT ACCIDENT was published by US NRC. The chemical element in generated debris will be dissolved in the containment spr...

Development of Detection Device Pressure Vessel for Control Rod Position Sensor in Nuclear Power Plants

Wang Yongchao, Fan Kai, JIang Shenghan, Zhang Bin, CAo Qi, LI Yun, Feng Weiwei

2017, 38(S2): 160-163. doi: 10.13832/j.jnpe.2017.S2.0160

Abstract(19) PDF(0)

Abstract:
The pressure vessel design scheme was completed based on the structure features and function requirements for the step-type control rod position sensor of Tianwan Nuclear Power Plant. The pressure vessel was mainly formed by the upper head, the cylinder body and the lower head. According to standard...

Analysis of Effect of Low Pressure Critical Heat Flux

Wu Xiaohong, Zhao Erlei, Zan Yuanfeng, LI Pengzhou, Zhuo Wenbin

2017, 38(S2): 164-166. doi: 10.13832/j.jnpe.2017.S2.0164

Abstract(22) PDF(0)

Abstract:
This paper mainly presents the test section, measure of parameters, technique research of low pressure CHF（critical heart flux） experiment and analysis of experimental result. In the experimental study, experimental methods and key experimental technique are explored by a uniformly heated vertical t...

Study on Fracture Failure Characteristics of Instrument Casing in Nuclear Power Plants

Yan Liang, LI Yang, Song Mingliang

2017, 38(S2): 167-171. doi: 10.13832/j.jnpe.2017.S2.0167

Abstract(19) PDF(0)

Abstract:
In this paper, the analysis on the casing and cladding metal were carried out by macro and micro methods, including the chemical composition analysis, microstructure analysis, fracture metallography and scanning electron microscopy（SEM）. The results showed that the microstructure and hardness of the...

Effect of Back Pressure on Pressurizer Safety Valve

Zhang Donglin, Yuan Shengyi, Wang Yuxiang, Guo Song, Yang Yong, Luo Shihong

2017, 38(S2): 172-174. doi: 10.13832/j.jnpe.2017.S2.0172

Abstract(32) PDF(0)

Abstract:
The effect of back pressure on opening and closing pressure, capacity and tightness of safety valve is analyzed in this paper. According to the analysis and computing, the effect is slight when the back pressure fluctuates. The reasonable design of pilot valve disk and bellow’s sealing areas can red...

Research on Fatigue Monitoring System Development for Nuclear Power Plants

Zhao Chuanli, Chen Yinqiang, Xu Feng, He Ziang, JI Yuanyuan

2017, 38(S2): 175-178. doi: 10.13832/j.jnpe.2017.S2.0175

Abstract(22) PDF(0)

Abstract:
The difference of the international fatigue monitoring systems were compared. As the key technologies of fatigue monitoring system development, the processing of operational load data and the stress influencing function development at monitored locations were researched in the paper. Finally, the on...

Reducing Low Pressure Injection Pump Vibration with Orifice in VVER

Zhou Zhijun, Zhang Shuai, He Ziang

2017, 38(S2): 179-181. doi: 10.13832/j.jnpe.2017.S2.0179

Abstract(21) PDF(0)

Abstract:
This paper analyzes the free end vibration of low-pressure injection pump, during the commissioning test on unit 3 of Tianwan Nuclear Power Plant.Through the quantity of orifice plates and optimization of aperture calculation, the pump and pipeline vibration problems are solved. It provides importan...

Application of Nonlinear Iteration Method in Reactor Real-Time Simulation

Duan Xinhui, Wang Bingshu, JIang Ping

2017, 38(S2): 182-187. doi: 10.13832/j.jnpe.2017.S2.0182

Abstract(25) PDF(0)

Abstract:
It is difficult to satisfy both high precision and speed of the 3 D distribution calculation of reactor power, during the development of full scope simulator for nuclear power plants. A 3 D real-time simulation code is developed for reactor core based on the Nonlinear Iteration Method（NIM）. The coup...

2017 Vol. 38, No. S2