核动力工程

Calculation and Analysis of Xenon Poison Effect Curve in HFETR

Wang Hao, Liu Shuiqing, Ma Liyong, Yang Bin, Kang Changhu

2016, 37(1): 1-3. doi: 10.13832/j.jnpe.2016.01.0001

Abstract(31) PDF(0)

Abstract:
Numerical method is applied in this paper. By means of the improvement of program, the xenon effect curves under different working conditions on the basis of loading scheme in some cycle of HFETR is studied and calculated. Also, the xenon poison effect curves after scram on the conditions that HFETR...

Analysis of Moderator Temperature Effect for PBR of SNTP

Jiang Duoyu, Jiang Xinbiao, Wang Lipeng

2016, 37(1): 4-7. doi: 10.13832/j.jnpe.2016.01.0004

Abstract(26) PDF(0)

Abstract:
The moderator temperature effect is positive of the particle bed reactor（PBR） model of SNTP, which will have a bad influence on the core safety. The changes of neutron spectra of reactor core, neutron production rates, neutron absorption rates and leakage rates at different ⁷LiH moderator temperatur...

Analysis of Complex Nuclide Chain Equation Calculation Based on Different Method

Tang Songqian, Xiao Feng, Tan Yi, Wei Shuping

2016, 37(1): 8-12. doi: 10.13832/j.jnpe.2016.01.0008

Abstract(17) PDF(0)

Abstract:
Depletion calculation of a large number of isotopes plays a very important role in many fields, and ORIGEN-S is the most widely used complex nuclide chain equation calculation code. In this paper, the theory of ORIGEN-S is presented, the time-dependent burnup matrix is explorted and solved using Che...

Application of Diagonally Implicit Runge Kutta in Point Kinetics

Zhang Zhizhu, Cai Yun, Peng Xingjie, Li Qing, Qin Dong

2016, 37(1): 13-17. doi: 10.13832/j.jnpe.2016.01.0013

Abstract(29) PDF(0)

Abstract:
The stiffness of point kinetics is very strong, while it usually takes a lot of time to solve by using full implicit Runge Kutta（FIRK）. Diagonally Implicit Runge Kutta（DIRK） is a useful tool like FIRK to solve the stiff differential equations, while it greatly reduces the computation compared with F...

Theoretical Research on DNB-type Critical Heat Flux with Non-Uniform Axial Heat Flux Distribution

Zhao Dawei, Liu Wenxing, Xiong Wanyu, Zan Yuanfeng, Yang Zumao

2016, 37(1): 18-22. doi: 10.13832/j.jnpe.2016.01.0018

Abstract(26) PDF(0)

Abstract:
Based on the liquid sublayer dryout mechanism, an improved mechanistic DNB-type critical heat flux（CHF） model has been developed for non-uniform axial heat flux distribution. In this DNB-type critical heat flux model, the non-uniform heat flux in axial is taken into account of upstream memory effect...

Numerical Investigation of Subcooled Flow Boiling Based on Experimental Data in Vertical Rectangular Narrow Channel

Chen Weihong, Yang Lixing, Zhang Hong

2016, 37(1): 23-27. doi: 10.13832/j.jnpe.2016.01.0023

Abstract(30) PDF(1)

Abstract:
This paper proposes and discusses a new wall boiling model developed based on our previous experimental work for the 2mm narrow rectangular channel. The new model includes the active nucleation site density, bubble departure diameter, bubble departure frequency and the onset of nucleate boiling（ONB）...

Evaluation and Analysis of Forced Convection Heat Transfer Correlations for Supercritical Carbon Dioxide in Tubes

Huang Yanping, Liu Shenghui, Liu Guangxu, Wang Junfeng, Zan Yuanfeng, Lang Xuemei

2016, 37(1): 28-33. doi: 10.13832/j.jnpe.2016.01.0028

Abstract(32) PDF(0)

Abstract:
This paper presents a review of typical heat transfer correlations for S-CO₂, and all of these reviewed correlations were preliminarily evaluated based on amounts of experimental data in published literatures. The results show that there exists superior difference between the predicted and experimen...

Study on Steam Condensation Model of A PRS Heat Exchanger

Rao Yuxian, Yu Lei, Fu Shengwei

2016, 37(1): 34-37. doi: 10.13832/j.jnpe.2016.01.0034

Abstract(21) PDF(0)

Abstract:
Steady-state calculations are performed using RELAP5/MOD3.2 code for a test facility which has the same size as one type of secondary-side passive residual heat removal system. In some conditions there are obvious differences between calculation results and experimental data. Thereby, the steam vert...

Experimental Research of Critical Heat Flux under Uniform Heating and Circumferential Nonuniform Heating in Vertical Circular Channel

Peng Jinfeng, Xu Jianjun, Huang Yanping, Liu Wenxing, Huang Hongwen, Peng Shuming

2016, 37(1): 38-42. doi: 10.13832/j.jnpe.2016.01.0038

Abstract(24) PDF(0)

Abstract:
In this paper, the critical heat flux（CHF） experiment in uniform heated and circumferential nonuniform heated vertical channels is developed for the sub-critical energy blanket in the fission-fusion hybrid energy system. The experiment forecast correlation, based on the critical heat flux experiment...

Effects of Wall Sub-Cooling on Local Heat Transfer for Forced Convection Condensation of Steam/air in A Horizontal Tube

Xu Huiqiang, Sun Qiunan, Gu Haifeng, Li Hao, Sun Zhongning

2016, 37(1): 43-47. doi: 10.13832/j.jnpe.2016.01.0043

Abstract(32) PDF(0)

Abstract:
For the purpose of analyzing the effects of wall sub-cooling on the heat transfer characteristics of forced convection condensation for steam/air mixtures in a horizontal tube, the experiments under air-cooling and water-cooling have been conducted. By comparing the experimental data for different i...

Fatigue Behavior of TA16 Tube with Surface Defect under High Cycle Loading

He Kun, Zhao Yuxiang, Dang Ying, Wang Li, Jiang Fan

2016, 37(1): 48-51. doi: 10.13832/j.jnpe.2016.01.0048

Abstract(29) PDF(0)

Abstract:
The high cycle fatigue behavior of TA16 alloy tube with the internal surface defect was evaluated. The defect of TA16 tube was examined by the method of ultrasonic flaw detection. Two kinds of TA16 tube were prepared: the traditional preparation technology has the crack-like and jagged defects, and ...

Coupled Numerical Simulation of Nuclear Fuel Particles Fluidization and CVD Reaction in Deposition Chamber for Niobium Coating

Li Tongye, Wang Hui, Chen Jianhua, Pan Xiaoqiang

2016, 37(1): 52-56. doi: 10.13832/j.jnpe.2016.01.0052

Abstract(24) PDF(0)

Abstract:
In order to study the agglomeration mechanism, the gas-solid flow field in the deposition chamber was numerically studied by Euler-Euler method, and the steady-state reduction reaction products were simulated by HSC Chemistry. Combined the flow field distribution and reduction reaction simulation, t...

Microstructure and Tensile Properties of 304L Austenitic Stainless Joints Produced by Friction Stir Welding and Tungsten Inert-Gas Welding

Xu Jiangming, Xu Chunrong, Fan Baoquan, Wang Shizhong

2016, 37(1): 57-61. doi: 10.13832/j.jnpe.2015.06.0057

Abstract(23) PDF(0)

Abstract:
3 mm thick 304 L austenitic stainless steel plates were welded by Friction Stir Welding（FSW） and Tungsten Inert-Gas Welding（TIG） respectively, then the microstructure and tensile properties of the welding joints of the two different types of welding were compared and analyzed. The results of the com...

Study on Automatic Control Method for Clod Start-up of Nuclear Power Plant

Yu Ren, Chen Zhi, Yang Huailei, Chen Yusheng, Xiao Kai, Liu Yang

2016, 37(1): 62-66. doi: 10.13832/j.jnpe.2016.01.0062

Abstract(23) PDF(0)

Abstract:
The overall control tactics for the automatic clod start-up of nuclear power plant is discussed in the paper. Then, different control methods are designed to realize the auto-control of the primary loop coolant temperature, the levels of the temperature, the pressure and the water of the pressurizer...

Study on Reasonability of Accident Conditions Load Combination for Nuclear Power Plant Primary Piping

Ai Honglei, Xie Hai, He Feng, Wang Xinjun, Lu Xifeng

2016, 37(1): 67-71. doi: 10.13832/j.jnpe.2016.01.0067

Abstract(28) PDF(0)

Abstract:
For verifying the reasonability of combination of SSE and LOCA which affect the nuclear power plant primary piping during accident conditions, the simultaneous SSE/LOCA effect on primary piping should be demonstrated that can not occur. Concluding from probability statistical analysis, the probabili...

Study on Critical Current of Movable Gripper Coil in CRDM Based on a Simplified Simulation Mechanism

Duan Yuangang, Qiang Wenjiang, Lan Yinhui, Huang Yili, Liu Feihua

2016, 37(1): 72-76. doi: 10.13832/j.jnpe.2016.01.0072

Abstract(21) PDF(0)

Abstract:
Based on the mechanical and magnetic structure near the movable gripper coil of magnetic type control rod drive mechanism, a simplified simulation mechanism with size ratio of 1:2 was set up. Based on this system, motion characteristics of the movable armature were studied. Both the magnetic circuit...

Research on the Dynamic Compensation Algorithm of Vanadium Self-Powered Neutron Detector Based on Robust Filtering Theory

Peng Xingjie, Zhang Zhizhu, Li Qing, Wang Kan

2016, 37(1): 77-81. doi: 10.13832/j.jnpe.2016.01.0077

Abstract(28) PDF(1)

Abstract:
Vanadium self-powered neutron detector（SPND） signal can be used to reconstruct core three-dimensional power distribution. Due to the delayed detector current response to flux variation, the dynamic compensation of the vanadium self-powered neutron detector current is needed to ensure the veracity of...

Development of Off-Line Leak Detection Device for Micro-Rupture Fuel Assemblies

Jia Yaqing, Li Chengye, Li Jinsong, Zhang Jinsong, Cheng Ying

2016, 37(1): 82-85. doi: 10.13832/j.jnpe.2016.01.0082

Abstract(24) PDF(0)

Abstract:
To solve the offline leak detection problem for the irradiated low burnup fuel assembly and micro-rupture which can not bedewatered, the research on technology of fuel assembly leak detection, pumping gas technology research and process checking research are carried out in this paper. Low temperatur...

Study on Leak Detection for Passive Residual Heat Remove System

Wang Yu, Chen Zhihui, Hao Chengming, Sun Yan, Huang Wei

2016, 37(1): 86-90. doi: 10.13832/j.jnpe.2016.01.0086

Abstract(19) PDF(0)

Abstract:
Heat transfer model of inlet tube is established for Small PWR（ACP100） passive residual heat removal system. The heat transfer mechanism for the leakage of inlet line and passive residual system is researched. The results show that the temperature instrument located more than 0.3 m below the inlet l...

Application of Reliability and Technique Centered Maintenance（RtCM) Method in Moisture Separator Reheater System of A Nuclear Power Plant

Cheng Bin, Zhang Guanghui

2016, 37(1): 91-94. doi: 10.13832/j.jnpe.2016.01.0091

Abstract(20) PDF(0)

Abstract:
Reliability and technique centered maintenance（RtCM） is a systematic engineering method used to determine the preventive maintenance requirement of equipment assets and optimizing the maintenance system. This paper has introduced the process and technological innovation of RtCM method through a prac...

Analysis of Root Cause for Safety Valve Leak

Kang Pengcheng, Hu Jun

2016, 37(1): 95-98. doi: 10.13832/j.jnpe.2016.01.0095

Abstract(23) PDF(0)

Abstract:
The special research is carried out on the leakage problem of the safety valve used in the field test. The main failure cause of safety valve has been found by dismantled them into parts, by checking the surfaces and the major dimensions, and analysis and inspection of the initial reason, measuring ...

Analysis of Reactor Lower Core Support Plate Heat Treatment Distortion and Repair

Chen Miaoxin, Wu Zhiyuan

2016, 37(1): 99-102. doi: 10.13832/j.jnpe.2016.01.0099

Abstract(18) PDF(0)

Abstract:
The flatness of the lower core support plate and the position of the fuel alignment pin holes were found deviated from the design requirements due to the heat treatment distortion during the manufacturing of the reactor vessel internals for the Haiyang Nuclear Power Plant Unit 1. The designer provid...

Fault Detection Design for Reactor Protection System of Hainan Changjiang Nuclear Power Station

Luo Wei, Feng Wei, Liu Hongchun, Wang Yinli, Xu Dongfang

2016, 37(1): 103-108. doi: 10.13832/j.jnpe.2016.01.0103

Abstract(29) PDF(1)

Abstract:
Reactor protection system is a key part of instrument and control system in nuclear power plants. In order to detect the fault of the protection system equipment, validate the availability and assure the nuclear power plant safety, the periodic fault detection shall be applied. This paper introduces...

Study on Effects of Temperature-Power Curve on MSHIM Strategy

Wang Jinyu, Wang Chuang, Liu Tongxian

2016, 37(1): 109-112. doi: 10.13832/j.jnpe.2016.01.0109

Abstract(21) PDF(0)

Abstract:
This paper takes Qinshan phase II NPP（600 MW） as the research target, and applies different reactor temperature-power curves on the reactor, then studies the effects of different reactor temperature-power curves on MSHIM. The analysis indicates that through the optimization of the reactor temperatur...

Motion Simulation for Delivery Process of In-Service Inspection Equipment

Zhu Xingli, Tian Ting, Zhou Lifeng, Chen Shu

2016, 37(1): 113-116. doi: 10.13832/j.jnpe.2016.01.0113

Abstract(21) PDF(0)

Abstract:
AP1000 passive PWR steam generator and main pump is connected by welding, and these welds require in-service inspection. This paper focus on the 3D motion simulation route and its movement algorithm for inspection equipment, based on Open Inventor 3D engine. The developed 3D simulation system realiz...

Experimental Study on Bubble Velocity Characteristics in Water under Sway Motion

Wen Jing, Tan Sichao, Fu Xuekuan, Meng tao, Song Yulin

2016, 37(1): 117-122. doi: 10.13832/j.jnpe.2016.01.0117

Abstract(34) PDF(1)

Abstract:
Experimental study of bubble velocity characteristics under sway motion is carried out. An experimental system is designed and manufactured. A fast camera is used to record the behavior of the bubbles. By tracking the path of the bubbles, movement parameters of the bubble are obtained under differen...

Preliminary 3D Numerical Study on Flow Blockage Accident in Multi-layer Annular Flow Channels

Fan Wenyuan, Guo Yun, Peng Changhong

2016, 37(1): 123-128. doi: 10.13832/j.jnpe.2016.01.0123

Abstract(30) PDF(0)

Abstract:
The multi-layer annular fuel assembly, which is consisted of annular-type fuel plates, is easily blocked. It is necessary to study the flow and heat transfer behavior of the assembly under flow blockage condition. In this study, basic problems in three-dimensional investigation on flow blockage acci...

Numerical Research for Passive Residual Heat Removal Heat Exchanger under Natural Convection Condition

Ge Jian, Cong Tenglong, Zhang Wenwen, Tian Wenxi, Qiu Suizheng, Su Guanghui

2016, 37(1): 129-132. doi: 10.13832/j.jnpe.2016.01.0129

Abstract(24) PDF(0)

Abstract:
Computational fluid dynamics（CFD） methodology is adopted to simulate the fluid flow and heat transfer characteristics of the passive residual heat removal heat exchanger（PRHRHX）. The C-type tube region is modeled by the porous media method. The coupled heat transfer rate from the primary side fluid ...

Development and Application of a Sub-Channel Analysis Code in Ocean Environment

Xiang Xiong, Shan Jianqiang, Zhang Bo

2016, 37(1): 133-138. doi: 10.13832/j.jnpe.2016.01.0133

Abstract(32) PDF(0)

Abstract:
Based on the definition of the ocean environment, the calculation methods of additional force in heaving and rolling motion are analyzed, and the modified methods of momentum equations and boundary conditions are obtained. Based on these, the sub-channel code ATHAS, which is with self-owned intellec...

Accelerating Domain-Decomposed Parallel Matrix MOC with Multi-Domain Coupled PGMRES Algorithm

Wu Wenbin, Li Qing, Wang Kan

2016, 37(1): 139-142. doi: 10.13832/j.jnpe.2016.01.0139

Abstract(20) PDF(0)

Abstract:
In this paper, spacial domain-decomposed parallel Matrix MOC and relevant multi-domain coupled PGMRES accelerating algorithm were studied. In this algorithm, PGMRES from PETSc library was adopted to solve the angular flux of inner boundaries directly, thus improving the convergence rate. Numerical r...

Evaluation of Nuclear Safety-Critical Software Reliability of DCS

Liu Ying, Yang Ming

2016, 37(1): 143-147. doi: 10.13832/j.jnpe.2016.01.0143

Abstract(28) PDF(0)

Abstract:
This paper tries to choose Bayesian Belief Networks（BBN） method to build the evaluation models. The stage evaluation models are constructed based on NUREG-0800 BTP7-14. It finished the software real-time evaluation in stages using 13 first-level indexes, 74 second-level indexes, 326 third-level inde...

In-pile Application and Preliminary Performance Analysis of Silicon Carbide Composite Cladding

Li Wenjie, Gao Shixin, Chen Ping, Jiao Yongjun, Chen Bingde

2016, 37(1): 148-151. doi: 10.13832/j.jnpe.2016.01.0148

Abstract(19) PDF(0)

Abstract:
Silicon carbide composite cladding used as the fuel cladding material can improve many performances for a PWR. In order to evaluate the in-pile performance of silicon carbide composite cladding, fuel behavior models of FUPAC were modified. A preliminary analysis was also performed, and the results s...

Research on Impact Properties of Auxiliary Bearings in HTR-10 AMB Helium Circulator Based on Quasi-Static Method

Yang Lei, Yang Guojun, Shi Zhengang

2016, 37(1): 152-156. doi: 10.13832/j.jnpe.2016.01.0132

Abstract(34) PDF(0)

Abstract:
The AMB’s impact properties are studied in this paper based on AMB in the helium circulator for the 10 MW high temperature gas cooled reactor（HTR-10）. The impact force when the vertical rotor drops is calculated, and the amount of deformation of the auxiliary bearings is calculated based on the quas...

Study on Resin Type Selection in Liquid Radwaste System of CAP Nuclear Power Plant

Liu Jiean, Liu Dan, Wang Xin, Chen Bin, Weng Minghui

2016, 37(1): 157-161. doi: 10.13832/j.jnpe.2016.01.0157

Abstract(25) PDF(0)

Abstract:
Two types of gel cation resins with different cross-linking degrees（16% and 8%） are studied for the nuclear grade resin type selection in CAP（China Advanced Pressurized Water Reactor） series of Generation III nuclear power plants. The effect of different resin specifications on operation performance...

International R&D Activities of SCWR and Illumination

Zhou Zhiru, Huang Yanping, Zang Jinguang, Li Yongliang, Xiao Zejun

2016, 37(1): 162-166. doi: 10.13832/j.jnpe.2016.01.0162

Abstract(24) PDF(0)

Abstract:
Based on the nuclear strategies and technical plans, Japan, Europe, Canada, Russia, China and other countries are devoted to the R&D of the supercritical water cooled reactor（SCWR） technology and have achieved lots of progress. This paper summarizes the international activities of SCWR from the ...

2016 Vol. 37, No. 1