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The second International Symposium on Socially and Technically Symbiotic Systems (STSS2015);The 7th International Symposium on Symbiotic Nuclear Power Systems (ISSNP2015)

作者： Sun Shi-yan XIA Hong CHEN Zhi-hui YANG Bo LIU Mei-ru Fundamental Science on Nuclear Safety and Simulation Technology Laboratory College of Nuclear Science and TechnologyHarbin Engineering University Science and Technology on Reactor System Design Technology Laboratory Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China

In nuclear power plants,for rotating equipment,a normal method for monitoring the modes and diagnosing its fault is monitoring and analyzing its vibration or noise ***,the detected signals are usually the non-linear mixed signals produced by multiple pieces of equipment or their different *** order to distinguish equipment's status,Blind Source Separation technique need to be applied to separate the mixed signals,then equipment's mode can be distinguished *** existing mature BSS algorithms are based on the assumption of the linear *** it to the nonlinear mixed problem directly may cause failure or result in totally wrong *** this paper,we apply geometric algorithm to separate the mixed vibration simulation *** method follows the post-nonlinear mixing model assumption,and develops its separating measure exploiting the difference between a linear mixture and a nonlinear one from their distributions in a three-dimensional *** impeller pump,which is a typical rotating machinery in nuclear power plants,is chosen as the study *** build a three-dimensional model of a kind of impeller pump,use Finite Element Analysis method to create some correlative stress and mode analysis,decorate appropriate monitoring points to get the most intense vibration simulation signal in the pump,and then construct the mixed *** using the post-nonlinear geometric algorithm,the mixed vibration simulation signals of the pump are *** with correlation coefficient,the algorithm performs *** can obtain the same vibration peak frequency from the result as that from the source signals.

关键词： Blind Source Separation post-nonlinear model geometric algorithm the impeller pump vibration simulation signal

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Visible‐Light‐Promoted Nickel‐ and Organic‐Dye‐Cocatalyzed Formylation Reaction of Aryl Halides and Triflates and Vinyl Bromides with Diethoxyacetic Acid as a Formyl Equivalent

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Angewandte Chemie 2017年第6期129卷

作者： He Huang Xiangmin Li Chenguang Yu Yueteng Zhang Patrick S. Mariano Wei Wang Department of Chemistry and Chemical Biology University of New Mexico Albuquerque NM 87131 USA State Key Laboratory of Bioengineering Reactor and Shanghai Key Laboratory of New Drug Design School of Pharmacy East China University of Science & Technology 130 Mei-Long Road Shanghai 200237 P.R. China

A simple formylation reaction of aryl halides, aryl triflates, and vinyl bromides under synergistic nickel‐ and organic‐dye‐mediated photoredox catalysis is reported. Distinct from widely used palladium‐catalyzed formylation processes, this reaction proceeds by a two‐step mechanistic sequence involving initial in situ generation of the diethoxymethyl radical from diethoxyacetic acid by a 4CzIPN‐mediated photoredox reaction. The formyl‐radical equivalent then undergoes nickel‐catalyzed substitution reactions with aryl halides and triflates and vinyl bromides to form the corresponding aldehyde products. Significantly, besides aryl bromides, less reactive aryl chlorides and triflates and vinyl halides serve as effective substrates for this process. Since the mild conditions involved in this reaction tolerate a plethora of functional groups, the process can be applied to the efficient preparation of diverse aromatic aldehydes.

关键词： Durchflusschemie Formylierungen Nickelkatalyse Photoredoxkatalyse Synthesemethoden

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Synthesis of Aldehydes by Organocatalytic Formylation Reactions of Boronic Acids with Glyoxylic Acid

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Angewandte Chemie 2017年第28期129卷

作者： He Huang Chenguang Yu Xiangmin Li Yongqiang Zhang Yueteng Zhang Xiaobei Chen Patrick S. Mariano Hexin Xie Wei Wang Department of Chemistry & Chemical Biology University of New Mexico Albuquerque NM 87131 USA State Key Laboratory of Bioengineering Reactor and Shanghai Key Laboratory of New Drug Design School of Pharmacy East China University of Science & Technology 130 Mei-Long Road Shanghai 200237 P.R. China

Reported herein is a conceptually novel organocatalytic strategy for the formylation of boronic acids. New reactivity is engineered into the α‐amino‐acid‐forming Petasis reaction occurring between aryl boronic acids, amines, and glyoxylic acids to prepare aldehydes. The operational simplicity of the process and its ability to generate structurally diverse and valued aryl, heteroaryl, and α,β‐unsaturated aldehydes containing a wide array of functional groups, demonstrates the practical utility of the new synthetic strategy.

关键词： Arene Bor Formylierungen Organokatalyse Synthesemethoden

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Nuclear Safety Improvement and R&D in NPIC for the Post Fukushima Era

Nuclear Safety Improvement and R&D in NPIC for the Post Fuku...

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2015欧亚经济论坛-2015第五届国际新能源产业大会

作者： Hongxing Yu Laboratory of Reactor Design Science and Technology Nuclear Power Institute of China

As the Three Mile Island and Chernobyl,the tragic Fukushima Dai-ichi Nuclear Power Plant accident occurring 4years ago has been the driving force to the safety improvement,its R&D and even for the next generation *** NPIC there are three dominant R&D fields:1) Safety improvement after Fukushima accident includes SBO evaluation and improvement,Seismic Margin Assessment(SMA) based on risk information,development and implementation of Severe Accident Management Guidelines,Severe Accident Expert Systems and etc.;2) R&D on nuclear safely covers fundamental research on key phenomena(*** degradation and reflooding,corium behaviour,hydrogen risks and etc.),Accident Tolerant Fuel(ATF),new methodology for coupling of PSA and deterministic safety analysis and etc.;3) design for GEN Ⅲ safely systems contains Cavity Injection System(CIS),Passive Removal System(PRS),passive containment cooling system and *** could be summarized that not only the safety of operating nuclear power plants and those under constructions has been enhanced due to these implements,but also the elaborative R&D are of significant value as the basement to finally achieve the practical elimination of large radioactive release.

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Neutron transport study based on assembly modular ray tracing MOC method

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Hedongli Gongcheng/Nuclear Power Engineering 2015年第3期36卷 157-161页

作者： Tian, Chao Zheng, Youqi Li, Yunzhao Li, Shuo Chai, Xiaoming School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an710049 China State Nuclear Power Software Development Center Beijing102200 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

It is difficulty for the MOC method based on Cell Modular Ray Tracing to deal with the irregular geometry such as the water gap between the PWR lattices. Hence, the neutron transport code NECP-Medlar based on Assembly Modular Ray Tracing is developed. CMFD method is used to accelerate the transport calculation. The numerical results of the 2D C5G7 benchmark and typical PWR lattice prove that NECP-Medlar has an excellent performance in terms of accuracy and efficiency. Besides, NECP-Medlar can describe clearly the flux distribution of the lattice with water gap. ©, 2015, Yuan Zi Neng Chuban She. All right reserved.

关键词： Ray tracing

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Analysis of RCS depressurization effects on containment temperature for Qinshan phase II nuclear power plant 22

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2014 22nd International Conference on Nuclear Engineering, ICONE 2014

作者： Lili, Liu Ming, Zhang Jian, Deng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Chengdu China

ISBN: (纸本)9780791845936

A severe accident code was applied for modeling of a typical pressurized water reactor (PWR) nuclear power plant, and the effects of RCS depressurization on the gas temperature of the relief tank cell in the containment during a station blackout (SBO) induced accident was analyzed. The sensitivity calculation indicated that the hydrogen generation rate obviously increased due to RCS depressurization in a critical stage. The results show that RCS depressurization can play an important role in hydrogen generation rate and total accumulation, and the temperature of the containment atmosphere is highly influenced by hydrogen combustion. High temperature induced by hydrogen combustion may degrade the equipment and instruments capabilities. Based on this analysis, a feasible strategy of RCS depressurization for mitigating the accident consequence is provided for developing the capacity of the SBO treatment of Qinshan Phase II Nuclear Power Plant (QSP-II NPP). Copyright © 2014 by ASME.

关键词： Nuclear power plants

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Study on material selection of reactor pressure vessel of SCWR

Study on material selection of reactor pressure vessel of SC...

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Energy Materials 2014

作者： Shuli, Ma Ying, Luo Qinwei, Yin Changxiang, Li Guofu, Xie Science and Technology on Reactor System Design Technology Laboratory NPIC Chengdu610041 China

ISBN: (纸本)9781119027942

This paper first analyzes the feasibility of SA-508 Grade 3 Class 1 Steel as an alternative material for Supercritical Water-Cooled reactor (SCWR) reactor Pressure Vessel (RPV). This kind of steel is limited to be applied in SCWR RPV due to its quenching property, though large forging could be accomplished by domestic manufacturers in forging aspect. Therefore, steels with higher strength and better quenching property are needed for SWCR RPV. The chemical component of SA-508 Gr.3 Cl.2 steel is similar to that of SA-508 Gr.3 Cl.1 steel, and more appropriate matching of strength and toughness could be achieved by the adjusting the elements contents, as well as proper control of tempering temperature and time. In light of the fact that Cl.2 steel has been successfully applied to steam generator, it could be an alternative material for SWCR RPV. SA-508 Gr.4N steel with high strength and good toughness is another alternative material for SCWR RPV. But large amount of research work before application is still needed for the lack of data on welding and irradiation etc.

关键词： Water cooled reactors

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Research on the domestic materials of forging Z12CN13 stainless steel for Hold-Down Spring of reactor

Research on the domestic materials of forging Z12CN13 stainl...

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Energy Materials 2014

作者： Li, Ning Ying, Luo Xin, Xia Hua, Du National Key Laboratory of Science and Technology on Reactor System Design Technology Chengdu610041 China

ISBN: (纸本)9781119027942

Effects of main alloying elements, quenching and tempering temperatures and quenching cooling velocity on mechanical properties of Z12CN13 stainless steel were obtained by controlling the material composition and optimizing the heat treatments. Evaluation of domestic forging Z12CN13 stainless steel for Hold-Down Spring of reactor had been completed, and all parameters met the requirement of design criteria national standard. The main alloying elements should be selected from upper limits to reach the technical standards of the strength and toughness properties. The strength, plasticity and toughness properties of domestic forging Z12CN13 stainless steel will decrease with increasing the quenching temperature. On the contrary, the strength decreases, plasticity and the toughness properties will increase with the increasing of tempering temperature. The tensile strength and impact toughness of materials are influenced obviously with the quenching cooling velocity. Improving the cooling velocity could meet the technical standards of the strength and toughness properties. The comprehensive mechanical properties and combination of strength and toughness is the best when the domestic forging Z12CN13 stainless steel is quenched at 985°C and then cooling fast and aged at 640°C.

关键词： Stainless steel

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Validation of sop procedure for dealing with FWLB 22

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2014 22nd International Conference on Nuclear Engineering, ICONE 2014

作者： Yaou, Shen Wei, Chen Daishun, Huang Guijun, Leng Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9780791845936

The State Oriented Procedure (SOP) is developed to improve the existing emergency operation procedures, namely, the Event Oriented Procedure (EOP). It is developed based on the finite Nuclear Steam Supply System (NSSS) states instead of an infinite number of possible events, therefore it can cover all of the events/accidents including the accidents caused by more than one initial event. On the other hand, the operator can take actions without diagnosing the events/accidents according to SOP, and thus the human mistakes which will possible happen during the events/accidents diagnosing can be avoided. However, as a generalized procedure system, the SOP needs a lot of validations based on various events/accidents. In this work, an analysis of a postulated Feed Water Line Break (FWLB) accident for LingAo phase II NPP based on the SOP is given and both the automatic protections and operator manual actions required by the SOP are modeled with an advanced, two-fluid, thermal-hydraulic code called CATHARE. The initial conditions and assumptions are chosen to get a severe state of the NPP. Since the EOP addresses the given accident perfectly, the results are then compared with those based on the EOP for a similar NPP to validate the SOP. The main parameters relevant with FWLB of this NPP are the same with LingAo phase II. Therefore, there is no need to perform analyses based on the EOP for LingAo phase II. The results demonstrate that the main operator manual actions required by the SOP are similar to those required by the EOP, and the operator can take the plant to a controllable safe state according to the SOP procedures. Therefore, the SOP is effective and reasonable for FWLB accident. Copyright © 2014 by ASME.

关键词： Nuclear engineering

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A study of heat transfer calculation method of reactor vessel metallic insulation 22

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2014 22nd International Conference on Nuclear Engineering, ICONE 2014

作者： Dapeng, Yan Luo, Ying Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu Sichuan China

ISBN: (纸本)9780791845899

Metallic insulation is commonly used in reactor vessel because of its resistance to radiation and corrosion. Since the main mode of heat loss of reactor vessel is thermal radiation, the ability to prevent radiation heat transfer is important for metallic insulation. But the thermal conductivity of metallic insulation is difficult to calculate owing to their complex geometry. This article uses FLUENT 14.0 to obtain the important parameter "view factor", and then develops a computational model of effective conductivity of metallic insulation. Heat transfer test of metallic insulation was done, and the numerical simulation of metallic insulation was also performed. Based on results of test and simulation, the computational model is modified. The modified model can fit the test result better. Based on the modified model, the effective conductivity of metallic insulation increases with the increase of temperature of hot side and cold side, among which the temperature of hot side influences more. And when the temperature is high, the effective conductivity increases much faster. Copyright © 2014 by ASME.

关键词： Heat radiation

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