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Development of three-dimensional neutron kinetics code based on high order nodal expansion method in hexagonal-Z geometry 26

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2018 26th International Conference on Nuclear Engineering, ICONE 2018

作者： Chao, Guo Yu, Liu Hangxing, He Luguo, Liu Xiaoyu, Wang Sufang, Xin Peiying, Li Xiaoli, Wu Hongsheng, Yuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9780791851456

To solve three-dimensional kinetics problems, a high order nodal expansion method for hexagonal-z geometry(HONEM) and a Runge-Kutta (RK) method are respectively adopted to deal with the spatial and temporal problem. In the HONEM, 1D partially-integrated flux are approximated by using four order polynomial. The two order polynomial is adopted to the approximation of partially-integrated leakages. The Runge-Kutta method is adopted as a tool for dispersing the time term of 3D kinetics equation. A flux weighting method (FWM) is used for obtaining homogenized cross sections of mix node. The three-dimensional hexagonal kinetics code has been developed based on this method and tested with two benchmark problems of VVER which are the control rod ejection without any feedback and with simple adiabatic Doppler feedback. The results calculated by this code agree well with the reference results and the code is validated. Copyright © 2018 ASME.

关键词： Runge Kutta methods

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Multiple branches coupling property and design of PRHRs

Multiple branches coupling property and design of PRHRs

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2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials

作者： Zhuohua, Zhang Xu, Ran Feng, Li Lin, Xian Ke, Zhou Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

Nuclear reactor applied on ship or floating platform recommend miniaturization and optimization of PRHRs. Due to much larger volume and heat transfer area in PRHRs heat exchanger, miniaturization and design of PRHRs need consider many constraints such as volume and systems configuration in containment. In normal reactor design such constraints are not so rigorous, but in reactor design for floating platform it takes significant difficulties. A multiple branches coupling system is constructed in the paper which describes the actual relationship between PRHRs and other systems or equipment, and by combining temperature distribution in heat exchanger and conservation equations of coupling system, the design parameters set satisfied design requirement can be calculated and optimization of design can be completed by programming solving method. Copyright © 2018 AMERICAN NUCLEAR SOCIETY, INCORPORATED, LA GRANGE PARK , ILLINOIS 60526Printed in USA.

关键词： Heat transfer

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Unraveling anisotropic corrosion behaviors of CoCrMo biomedical alloy fabricated by laser powder bed fusion: Microstructure heterogeneity insights

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Journal of Alloys and Compounds 2025年

作者： Li Zhang Jian Tu Yingrui Liu Xingqun Zhang Li Yang Yanxiang Liang Yanbin Du Jinru Luo Shuqian Fan College of Material Science and Engineering Chongqing University of Technology Chongqing 400054 PR China Chongqing Materials Research Institute Co. Ltd Chongqing 400707 China Chongqing Institute of Green and Intelligent Technology Chinese Academy of Sciences Chongqing 400714 PR China State Key Laboratory of Rail Transit Vehicle System Southwest Jiaotong University Chengdu 610031 PR China Chongqing Key Laboratory of Manufacturing Equipment Mechanism Design and Control Chongqing Technology and Business University Chongqing 400067 PR China Department of Ferrous Metallurgy University of Science and Technology Beijing Beijing 100083 China JITRI Advanced Materials R&D Co. Ltd. Yangtze Delta Suzhou 215133 China

CoCrMo biomedical alloys are extensively used in medical implants for their superior biocompatibility and mechanical properties. The present study investigates the relationship between microstructure and corrosion behavior on the building surface (XY-plane) and side surface (YZ-plane) of CoCrMo alloys fabricated by laser powder bed fusion (LPBF). Comprehensive electrochemical tests revealed significant anisotropy in corrosion behavior between the XY and YZ planes due to the microstructure heterogeneity. In the XY-plane, finer grain sizes, higher dislocation densities, longer sub-grain boundaries, and a more extensive distribution of inclusions facilitate the formation and stability of a dense protective film, effectively preventing the intrusion of corrosive media. In contrast, the YZ-plane, characterized by a higher density of melt pool boundaries (MPBs), demonstrated pronounced selective corrosion, particularly within the sub-grain regions and along the MPBs. These insights can guide the optimization of manufacturing processes to enhance corrosion resistance, thereby improving the performance and safety of medical implants by reducing the risk of implant failure due to corrosion-related issues.

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Preliminary study on few group cross section representation method based on model tree algorithm

Preliminary study on few group cross section representation ...

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2018 International Conference on Physics of reactors: reactor Physics Paving the Way Towards More Efficient systems, PHYSOR 2018

作者： Zhao, Wenbo Ju, Haitao Yu, Yingrui Chai, Xiaoming Yu, Junchong Peng, Xingjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

ISBN: (纸本)9781713808510

The tabular representation of few-group cross section is widely used for node wise two-step core simulations. However, it may take too much memory usage for pin-by-pin two-step simulations. A few-group cross section representation method for PWR has been developed to reduce memory usage in this paper. The few-group cross sections are represented as the sum of a base term and a collection of partial terms. Each of these terms is fitted by modified model tree. The case matrix of training data set is similar with that of the conventional methods such as the piece wise interpolation and the tabular representation. Two modifications have been made for the model tree algorithm: 1) burnup is the only variable to split data set, 2) linear regression method on nodes of the tree is replaced with polynomial fitting method according to priori knowledge of the relationship between cross sections and state variables. Through the modifications accuracy and generalization ability are achieved without the pruning procedure. Then the lattice calculations for test data set could be canceled. Tests on the typical PWR lattice are performed. Numerical results show that for the worst case the memory usage of this method is less than 30% of the tabular representation, when the maximum error of reactivity is less than 500 pcm. The memory usage for other cross sections is less than 10% with high accuracy. Optimization of the target tolerance criteria should be tested for fast group cross sections. Large errors in thermal group absorption and fission production cross sections lead to large errors in Kinf and it needs more study on regression model. The method combined with the tabular representation might be more suitable for the pin-by-pin two-step simulations. © 2018 International Conference on Physics of reactors, PHYSOR 2018: reactor Physics Paving the Way Towards More Efficient systems. All rights reserved.

关键词： Errors

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Maap5 simulation of pwr high-pressure core melting severe accident due to smallbreak loca

Maap5 simulation of pwr high-pressure core melting severe ac...

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2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018

作者： Wu, Xiaoli Li, Wei Deng, Jian Deng, Chunrui Hou, Liqiang Zhang, Dan Yuan, Hongsheng Science Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9780894487552

MAAP5 is capable of simulating the whole response of a PWR nuclear power plant under severe accident conditions. An analysis of the severe accident scenarios in a PWR by MAAP5 were carried out. It was assumed that the severe accident was initiated by an unusual smallbreak loss-of-coolant accident (SBLOCA) at the reactor pressure vessel (RPV) lower head and the failure of highpressure injection system (HPIS) in a PWR by using MAAP5 were carried out. Different break sizes with and without manual depressurization of the reactor coolant system (RCS) were studied. The results showed that without manually depressurization the RCS, reactor core underwent slow heatup and completely melted and eventually failed the RPV lower head at the primary system pressure of 6.87 MPa for 0.4-inch-break LOCA and 2.71 MPa for 1.0-inch-break LOCA. On the other hand, timely manually opening the pressurizer (PZR) safety valves (SVs) was an effective mitigation measure to recover the core coolabilty by cold-leg accumulator injection system (AIS) and low-pressure injection system (LPIS). Besides, reasonably manually opening the steam generators (SGs) SVs while keeping the auxiliary feedwater work also helped to depressurize the RCS and prevent the severe accident. Both of the two mitigation measures successfully prevented the core from complete melt, but the latter one is preferable to the former one provided no steam generator tube rupture took place. © 2018 American Nuclear Society. All rights reserved.

关键词： Loss of coolant accidents

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Multiple branches coupling property and design of PRHRs

Multiple branches coupling property and design of PRHRs

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AISTech 2018 Iron and Steel technology Conference and Exposition

作者： Zhuohua, Zhang Xu, Ran Feng, Li Lin, Xian Ke, Zhou Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9781935117728

关键词： Heat transfer

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Research on the response of core barrel under random turbulence excitation 25

Research on the response of core barrel under random turbule...

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25th International Congress on Sound and Vibration 2018: Hiroshima Calling, ICSV 2018

作者： Huang, Xuan Wu, Wan-Jun Qi, Huan-Huan Feng, Zhi-Peng Liu, Shuai Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China

ISBN: (纸本)9781510868458

The flow-induced vibration of reactor structures is directly related to nuclear safety and has long been closely watched by the nuclear engineering community. A large number of theoretical, experimental and numerical analysis research work are carried out at home and abroad. In one hand, the test means cost a lot of money and time;on the other hand due to the restriction of test conditions, we only can get the measurement results about part of the structure under specific conditions. Therefore, from the design point of view, the theoretical or numerical analysis methods should be developed to predict structural flow induced vibration response in order to compensate for the lack of test methods. For the purpose of completing the flow-induced vibration analysis of the components in the reactor, it is necessary to analyse the vibration characteristics of the components in the reactor. According to the fluid excitation situation, this paper based on the test study two kinds of core barrel calculation method of forced vibration response under turbulent excitation. The advantages and disadvantages of these two methods are described from the aspects of calculation model, calculation input, analysis method and calculation result. © 25th International Congress on Sound and Vibration 2018, ICSV 2018: Hiroshima Calling. All rights reserved.

关键词： Vibration analysis

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The implicit runge kutta method for solving point burnup equations

The implicit runge kutta method for solving point burnup equ...

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2018 Transactions of the American Nuclear Society, ANS 2018

作者： Cai, Yun Peng, Xingjie Li, Qing Qin, Dong Jiang, Zhumin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China

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Experimental investigation of abnormal transverse flow enhancement of α particles in heavy-ion collisions

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Physical Review C 2021年第4期104卷 044611-044611页

作者： Y. Huang W. Lin H. Zheng R. Wada A. Bonasera Z. Chen J. Han R. Han M. Huang K. Hagel T. Keutgen X. Liu Y. G. Ma C. W. Ma Z. Majka G. Qu L. Qin P. Ren G. Tian J. Wang Z. Yang J. B. Natowitz Key Laboratory of Radiation Physics and Technology of the Ministry of Education Sichuan University Chengdu 610064 China School of Physics and Information Technology Shaanxi Normal University Xi'an 710119 China Cyclotron Institute Texas A&M University College Station Texas 77843 USA School of Physics Henan Normal University Xinxiang 453007 China Laboratori Nazionali del Sud INFNvia Santa Sofia 62 95123 Catania Italy Institute of Modern Physics Chinese Academy of Sciences Lanzhou 730000 China College of Physics and Electronics Information Inner Mongolia University for Nationalities Tongliao 028000 China FNRS and IPN Université Catholique de Louvain B-1348 Louvain-Neuve Belgium Key Laboratory of Nuclear Physics and Ion-Beam Application (MOE) Institute of Modern Physics Fudan University Shanghai 200433 China Shanghai Institute of Applied Physics Chinese Academy of Sciences Shanghai 201800 China Jagiellonian University Krakow Poland School of Science Huzhou University Huzhou 313000 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu 610213 China

The mass dependence of the transverse flow for Z=1–5 fragments from the collisions of Ar40+Al27, Ar40+Ti48, and Ar40+Ni58 at 47 MeV/nucleon is investigated experimentally in this article. The transverse flow values are determined using the in-plane components of the fragment transverse momenta, where three conventional methods, i.e., the kinetic flow tensor method, the transverse momentum analysis method, and the azimuthal correlation method, are applied to reconstruct the reaction plane in an event-by-event basis. It is demonstrated from the comparison of the present experimental mass dependent flow measurements and the model simulations using an improved antisymmetrized molecular dynamics model that the experimentally observed abnormal α transverse flow enhancement is closely related to the reaction plane reconstruction procedure in the flow extraction. We further investigate the physical existence of the abnormal α flow behavior using a two-particle azimuthal correlation method, which allows us to provide the relative flow magnitude information with an identification of fragment charge number without the knowledge of the reaction plane differing from the three conventional methods. It is found that the relative flow magnitudes deduced from the two-particle azimuthal correlation functions with an identification of Z, with the correction for the recoil effect imposed by the momentum conservation, show a monotonically increasing trend as a function of fragment charge number, with no exception of the α flow enhancement. These results, in addition to those from the improved antisymmetrized molecular dynamics model simulations, definitely provide experimental evidences for the inexistence of the abnormal α flow behavior in the heavy-ion collisions at the present incident energy region in nature.

关键词： Collective flow Low & intermediate energy heavy-ion reactions Nuclear reaction analysis

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Development of the Insect-inspired Biomimetic Underwater Microrobot for a Father-son Robot system

Development of the Insect-inspired Biomimetic Underwater Mic...

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IEEE International Conference on Mechatronics and Automation

作者： Wenbo Sui Shuxiang Guo Liang Zheng Ruochen An Awa Tendeng Graduate School of Engineering Kagawa University Takamatsu Kagawa Japan Faculty of Engineering and Design Kagawa University Hayashi-cho Kagawa Japan Key Laboratory of Convergence Medical Engineering System and Healthcare Technology the Ministry of Industry and Information Technology School of Life Science Beijing Institute of Technology Beijing China Tianjin Key Laboratory for Control Theory and Application in Complicated Systems and Intelligent Robot Laboratory Tianjin University of Technology Tianjin China

ISBN: (数字)9781728164168

ISBN: (纸本)9781728164175

In this paper, the lifting platform structure of the father robot and the development of the insect-inspired biomimetic underwater microrobot are presented. The objective is to decrease the load of microrobot and realize more functions. In previous researchers, the platform of the father robot is fixed, which is not conducive to adopt and release the son robot. The structure of the lifting platform can effectively solve the problem in theory. The insect-inspired microrobot used wood which has high hydrophilism. It causes the body of microrobot increased weight and short-term works. The fillable structure with waterproof character which is made by a 3D printer. The new structure also can be changed weight for achieving different functions underwater efficiently. Then, two kinds of communication between the light source and microrobot like chasing rotation and fixed distance chasing are described in order to prove the feasibility of the software. In all these cases, experimental results show the performance of the microrobot.

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