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Journal of Wuhan University of Technology(Materials Science) 2024年第5期39卷 1061-1072页

作者： WEI Hongming LI Mingchao LI Xiaoya ZHAN Wenyi LI Feiyang DAI Yanzhang ZOU Jianpeng State Key Laboratory of Powder Metallurgy Central South UniversityChangsha 410083China guangxi fangchenggang nuclear power co. Ltd.Fangchenggang 538000China

We review the fundamental properties and significant issues related to Cu/graphite *** particular,recent research on the interfacial modification of Cu/graphite co.posites is addressed,including the metal-modified layer,carbide-modified layer,and co.bined modified ***,we propose the use of ternary layered carbide as an interface modification layer for Cu/graphite co.posites.

关键词： Cu/graphite co.posites interfacial bonding surface modification wettability layered ternary carbides

Influence of Hyperon-Hyperon Interaction on Properties of Hadronic Star

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co.munications in Theoretical Physics 2010年第1期53卷 133-137页

作者：米爱军尤伟 China nuclear power Engineering co. Ltd.

The influences of hyperon-hyperon interaction on the overall properties of hadronic star are investigated in the framework of relativistic mean field （RMF） theory. For certain hyperon co.pling, the weaker hyperon-hyperon interaction can lead to the heavier hadronic star, which acco.ds with the observation of heavy neutron star in X-ray binaries. We find that the threshold densities of the hyperons with larger masses are brought to a lower values with the increase of the hyperon-hyperon interaction. The possibility of the existence of hyperon star is checked with the co.sideration of hyperon-hyperon interaction.

关键词： hyperon interaction relativistic mean field theory hadronic star

HPR1000： Advanced Pressurized Water Reactor with Active and Passive Safety

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Engineering 2016年第1期2卷 79-87页

作者： Ji xing Daiyong Song Yuxiang Wu China nuclear power Engineering co. Ltd. Beijing 100840 China

HPR1000 is an advanced nuclear power plant(NPP)with the significant feature of an active and passive safety design philosophy,developed by the China National nuclear *** one hand,it is an evolutionary design based on proven technology of the existing pressurized water reactor NPP;on the other hand,it inco.porates advanced design features including a 177-fuel-assembly co.e loaded with CF3 fuel assemblies,active and passive safety systems,co.prehensive severe accident prevention and mitigation measures,enhanced protection against external events,and improved emergency response *** verification experiments and tests have been performed for critical innovative improvements on passive systems,the reactor co.e,and the main *** design of HPR1000fulfills the international utility requirements for advanced light water reactors and the latest nuclear safety requirements,and addresses the safety issues relevant to the Fukushima *** with its outstanding safety and eco.omy,HPR1000 provides an excellent and practicable solution for both domestic and international nuclear power markets.

关键词： HPRI000 Active and passive safety Advanced nuclear power reactor

Effects of interstitial cluster mobility on dislocation loops evolution under irradiation of austenitic steel

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nuclear Science and Techniques 2024年第8期35卷 69-78页

作者： Xin‑Hua Yan Lu Sun Du Zhou Teng Xie Chang Peng Ye‑Xin Yang Li Chen Zhen‑Feng Tong North China Electric power University Beijing 102206China China nuclear power Operations co. LtdShenzhen 518000China

The evolution of dislocation loops in austenitic steels irradiated with Fe^(+)is investigated using cluster dynamics(CD)simulations by developing a CD *** CD predictions are co.pared with experimental results in the *** number density and average diameter of the dislocation loops obtained from the CD simulations are in good agreement with the experimental data obtained from transmission electron microsco.y(TEM)observations of Fe~+-irradiated Solution Annealed 304,co.d Worked 316,and HR3 austenitic steels in the *** CD simulation results demonstrate that the diffusion of in-cascade interstitial clusters plays a major role in the dislocation loop density and dislocation loop growth;in particular,for the HR3 austenitic steel,the CD model has verified the effect of temperature on the density and size of the dislocation loops.

关键词： Cluster dynamics Dislocation loops In-cascade interstitial clusters Austenitic steels

Reco.mendations on legislative and regulatory framework and regulatory body of nuclear security in China

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nuclear Science and Techniques 2007年第5期18卷 307-310页

作者： PU Jilong LI Xiaoyan China Guangdong nuclear power Holding co. Ltd. Shenzhen 518031 China

This paper describes the definition of nuclear security that has been changing from the co.d war age to the post-911 period, and clarifies the close relationship and yet a clear distinction between nuclear security, nuclear safety and nuclear safeguard. Based on analyses of the current state of nuclear security activities in China as well as the requirements and the law infrastructure, a legislative and regulatory framework of nuclear security and the mandate of a regulatory body in China are reco.mended.

关键词：核安全立法反应堆安全管理

Analysis of the influence on environmental radiation level of Qinshan area caused by Fukushima nuclear accident

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nuclear Science and Techniques 2014年第A1期25卷 66-70页

作者：高阳朱月龙 CNNC nuclear power operations management co. Ltd. Zhejiang 314300 China

In order to monitor the diffusion and deposition of radioactive plume in Qinshan area after Fukushima nuclear accident, a co.tinuous air sampling was did from March 25 to May 6. A trace of 134Cs and 131I were detected in the period. Results of co.ventional environmental radiation monitoring also showed that the specific activity of 90Sr and 137Cs in environmental samples had some abnormal changes in 2011 which almost felt back to normal level in 2012. Although there is no abnormal change on environmental radiation level of Qinshan area till now, the influence caused by Fukushima nuclear accident should be paid co.tinuously attention in future by radiation monitoring. © 2014, Science Press. All rights reserved.

关键词：环境辐射水平核事故山地监测结果放射性烟云铯-137 环境样品辐射监测

Characteristic Analysis of AC Plasma Arc in Water

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Plasma Science and Technology 2011年第1期13卷 111-114页

作者：周恩平杨嘉祥马凤莲 co.lege of Electrical and Electronic Engineering Harbin University of Science Technology Liaoning Hongyanhe nuclear power co. LTD

An experimental system of AC arc discharge in water was designed with pole-pole electrodes and a peak voltage of 1500 V and a test circuit was set up using virtual instrument technology. The mechanism of an AC plasma arc generated in water was analyzed. The voltage- current characteristic of the AC plasma are was obtained from the waveform. The temperature characteristic was tested with a spectrum diagnosis system, and the effect of different electrode materials on the striking voltage and peak current was analyzed. The results show that when a power supply of 6 kW is applied on electrodes with a gap of 2 mm in water, the striking voltage is from 900 V to 1300 V, the arc voltage is from 40 V to 100 V, the arc current is from 2 A to 7 A, and the zero rest period is from 1 ms to 2 ms. In addition, the arc voltage and current are different for electrodes in aluminum, co.per and stainless steel. The arc voltage is lower and the current is higher for an aluminum electrode than those for co.per and stainless steel ones. The highest temperature of the arc is 7643 K.

关键词： discharge in water AC plasma arc V-I characteristics temperature charac- teristics electrode material characteristics

Diffusion process for efficiency improvement with high sheet resistance on traditional production lines of solar cell

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Science China(Technological Sciences) 2014年第5期57卷 962-967页

作者： JIA HeShun LUO Lei JIANG YanSen XU ZhenHua REN XianKun ZHANG ChunYan Shandong Linuo Solar power Holdings co. Shandong Province nuclear and Radiation Safety Testing Center

By optimizing the diffusion temperature and time,four groups of samples with different sheet resistances are *** front screen printing pattern and firing temperature are fine-tuned acco.ding to the *** performance of the low-and-plateau-temperature doping recipe(as recipe A)is better than that of the low-and-multiple-temperature doping recipe(as recipe B).And the 19.24%efficiency of volume production of monocrystalline solar cells with 238.95 mm2 and 80?/sq sheet resistance is obtained in the traditional process line.0.48%more efficiency is achieved than 60?/sq due to the reduction of the phosphorus surface doping and shallow junction by the low-and-plateau-temperature diffusion *** module test shows that by using two drive-in zones,not only do we have a higher efficiency,but also have a stabler and lower power loss in encapsulation *** is showed that power of a large improvement will be gotten by statistical analysis and PC1D simulation.

关键词： solar efficiency simulation power loss

Improvement on application of Danco.f factor and resonance interference table

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nuclear Science and Techniques 2016年第2期27卷 122-130页

作者： Yu Han Xiao-Feng Jiang De-Zhong Wang School of nuclear Science and Engineering Shanghai Jiaotong University Shanghai 200240 China Shanghai NuStar nuclear power Technology co. Ltd.Shanghai 200000 China

An improvement for application of Danco.f factor is developed. It co.bines Stamm'ler's two-term method for resonance integral calculation with neutron current method for Danco.f factor calculation. Stamm'ler's formulation, which is originally derived for the infinite lattice geometry, can be easily revised to co.tain the Danco.f factor explicitly, while the neutron current method can easily calculate the Danco.f factor for general irregular assembly geometry. For the resonance interference effects the resonance interference factor table is built in pairs of nuclides, only for the interference between 238 U and other resonance nuclides, spanning over a range of background cross-section and number density ratio of the pairing nuclides. A series of verification calculations have been carried out for problems of infinite lattice and single assembly geometry, with two or multiple resonance absorbers. For these verification calculations, our improvement on Danco.f factor application and resonance interference give good results.

关键词：共振干涉因子和应用积分计算几何形状干涉效应中子流核素

Effect of multiple heat treatments on fracture property of centrifugal casting stainless steels Z3CN20.09M with long-term thermal aging degradation

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Journal of Iron and Steel Research International 2021年第2期28卷 223-231页

作者： Min-yu Fan Wen-qing Jia Wei-wei Yu Dong-ying Wang Meng Guan Yu Cao Fei Xue Yin-li Liu Jing-wen Yao Bin Lin Ting Yu Suzhou nuclear power Research Institute Suzhou 215004JiangsuChina Shenyang Blower Works Group nuclear Pump co. Ltd.Shenyang 110869LiaoningChina

It is of great significance to investigate effect of multiple heat treatments on fracture property of centrifugal casting stainless steels Z3CN20.09M cut from pump casing with long-term thermal aging degradation for nuclear power plants to co.sider actual operation of nuclear power *** multiple heat treatments and accelerated thermal aging experiment at the same temperature of 400℃ for different time were successively carried out on centrifugal casting stainless steels Z3CN20.09M in order to examine the metallographic modification and impact ***,an additional investigation on the related fracture properties was carried out,in which the critical initial fracture toughness Ji was determined by stretch zone width and 0.2 mm offset line *** results indicated that the multiple heat treatments led to the dispersed distribution of ferrite phases in austenite matrix and thus microhardness increased,but impact energy exhibited a decreasing tendency *** long-term aging,the metallographic structure remained almost unchanged,but the size of ferrite phases showed a slight increasing trend because of spinodal deco.position in ferrite phases and G-phase *** addition,centrifugal casting stainless steels Z3CN20.09M with multiple heat treatments exhibited the higher microhardness,Charpy impact toughness,critical initial fracture toughness J_(IC)(J-integral determined by 0.2 mm offset line method),and J_(SZW)(J-integral determined by stretch zone width method)than those with primary heat treatment,while the specific number of the heat treatment had a low influence on fracture toughness.

关键词： Multiple heat treatment Z3CN20.09M cast stainless steel Impact property Fracture toughness Long-term thermal aging