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2018 Transactions of the American Nuclear Society, ANS 2018

作者： Hu, Yuying Luo, Qi Yao, Dong Yu, Yingrui Qiu, Liqing Liao, Hongkuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China China Nuclear Power Institute of China Chengdu610041 China

When the velocity of coolant water is 2m/s, 4 targets of 32.5g235U in 3# hole could produce more than 60,000Ci per year. Under this condition, targets are irradiated safely, and the largest production could be gained....

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Optimization Method for an Information Interaction Interface from Error-Cognition to Information Feature Mapping

Research Square

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Research Square 2020年

作者： Wu, Xiaoli Caldwell, Sabrina School of Design Art & Medial Nanjing University of Science & Technology Nanjing210094 China Research School of Computer Science The Australian National University ACT Australia College of Mechanical and Electrical Engineering Hohai University Changzhou China Lab of Human Factors and Information System Interaction & Design Hohai University Changzhou China

Background- With the rapid development of digital and intelligent information systems, display of visual information in interfaces has become an important challenge in the field of human-computer interaction. Objective- We propose a method for the optimization of information interaction interfaces from error-cognition through the mapping of information characteristics. Method- A mapping method of matrix description is adopted to analyze the association properties between error-cognition sets and design information sets. Results- Based on the mapping relationship between the domains of error-cognition and design information, a cross-correlational analysis is carried out between error-cognition and design information. Conclusion- We obtain the relationship matrix between the error-cognition of correlation between design information and the degree of importance among design information. Application- Taking the task interface of a warfare navigation display as an example, error factors and the features of design information are extracted. Based on the results, we also propose an optimization design scheme for the monitoring task interface. © 2020, CC BY.

关键词： Errors

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Connectors based on 2-way SMA actuator for self-reconfigurable chain robots 15

Connectors based on 2-way SMA actuator for self-reconfigurab...

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15th IEEE International Conference on Mechatronics and Automation, ICMA 2018

作者： Ni, Fenglei Li, Yongqiang Zhou, Yunhu Liu, Hong Tang, Yuan State Key Laboratory of Robotics and System Harbin Institute of Technology Harbin Heilongjiang Province China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9781538660720

Self-reconfigurable modular robots have shown great potential in carrying out multiple tasks in different conditions. A connection of both flexibility and reliability is critical for realizing the docking and transformation of the modular robots. We propose a new design of connectors based on SMA which has the advantages of high autonomy, small size and high speed. The couples of connectors consist of active and passive connector. In the active connector, a two-way rotary SMA actuator is used as the actuation mechanism. The double-layer cam and claws are used as an executive mechanism. The passive connector can be securely docked in five different facets for 3D reconfigurations. The multisensory system and hardware architecture provide the foundation for control strategies. The design and the prototype of the connector are described in this paper. Finally, experimental results to evaluate the performance of docking are presented. © 2018 IEEE.

关键词： Modular robots

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Determining impact parameters of heavy-ion collisions at low-intermediate incident energies using deep learning with convolutional neural network

arXiv

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arXiv 2021年

作者： Zhang, X. Huang, Y. Lin, W. Liu, Xingquan Zheng, H. Wada, R. Bonasera, A. Chen, Z. Chen, L. Han, J. Han, R. Huang, M. Hu, Q. Leng, Q. Ma, C.W. Qu, G. Ren, P. Tian, G. Xu, Z. Yang, Z. Zhang, L. Key Laboratory of Radiation Physics and Technology The Ministry of Education Sichuan University Chengdu610064 China School of Physics and Information Technology Shaanxi Normal University Xi’an710119 China Cyclotron Institute Texas A&M University College StationTX77843 United States Laboratori Nazionali del Sud INFN via Santa Sofia 62 Catania95123 Italy Institute of Modern Physics Chinese Academy of Sciences Lanzhou730000 China College of Physics and Electronics information Inner Mongolia University for Nationalities Tongliao028000 China School of Physics Henan Normal University Xinxiang453007 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China School of Information Sciences and Engineering Lanzhou University Lanzhou730000 China

A deep learning based method with the convolutional neural network (CNN) algorithm for determining the impact parameters is developed using the constrained molecular dynamics model simulations, focusing on the heavy-ion collisions at the low-intermediate incident energies from several ten to one hundred MeV/nucleon in which the emissions of heavy fragments with the charge numbers larger than 3 become crucial. To make the CNN applicable in the task of the impact parameter determination at the present energy range, specific improvements are made in the input selection, the CNN construction and the CNN training. It is demonstrated from the comparisons of the deep CNN method and the conventional methods with the impact parameter-sensitive observables, that the deep CNN method shows better performance for determining the impact parameters, especially leading to the capability of providing better recognition of the central collision events. With a proper consideration of the experimental filter effect in both training and testing processes to keep consistency with the actual experiments, the good performance of the deep CNN method holds, and shows significantly better in terms of predicting the impact parameters and recognizing the central collision events, compared to that of the conventional methods, demonstrating the superiority of the present deep CNN method. The deep CNN method with the consideration of the filter effect is applied in the deduction of nuclear stopping power. Higher accuracy for the stopping power deduction is achieved benefitting from the better impact parameter determination using the deep CNN method, compared to using the the conventional methods. This result reveals the importance to select a reliable impact parameter determination method in the experimental deduction of the nuclear stopping power as well as other observables. © 2021, CC BY.

关键词： Molecular dynamics

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Safety design and evaluation of loss of forced flow accident of CRS1000

Safety design and evaluation of loss of forced flow accident...

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

作者： Dan, Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Changshun Road No.328 ShuangLiu County Chengdu610213 China

ISBN: (纸本)9780894487552

CSR1000 (China supercritical water reactor, 1000MWe) was developed by NPIC, as BWR, the pressure vessel's reactor and directly circulate loop was adopted, however, the coolant will encounter double flow pass in the reactor. The passive engineering safety feature was adopted and the reactor residual heat will be removed by natural circulation of coolant. As above character, loss of feed water or loss of offsite power will cause completely loss of forced flow accident, the flow in first pass of core will encounter flow inversion during this course, these factor make the LOFA(Loss Of forced Flow Accident) become one of the most limiting accident in CSR1000. The LOFA was analyzed by APROS. The result shows, during the short time of LOFA, the passive operation of HFT will mitigate the accident, and during long term, the passive residual heat removal system will function and maintain the core within the safety state. © 2018 American Nuclear Society. All rights reserved.

关键词： Coolants

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Calculation of adjoint-weighted reactor kinetics parameters in OpenMC

Calculation of adjoint-weighted reactor kinetics parameters ...

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

作者： Peng, Xingjie Forget, Benoit Smith, Kord Science and Technology on Reactor System Design Technology Laboratory ChengduSichuan610000 China Nuclear Science and Engineering Department Massachusetts Institute of Technology 77 Massachusetts Ave. CambridgeMA02139 United States

ISBN: (纸本)9781713808510

Knowledge of adjoint-weighted kinetics parameters plays an importance role in analyzing the reactor safety and in describing the transient behavior of nuclear reactors during normal operation or accidents. In this work, the capability of calculating adjoint-weighted kinetic parameters, including the effective neutron generation time, the effective delayed neutron fraction, and the ratio of these two quantities was implemented in OpenMC code based on two different methods of interpreting the physical meaning of the adjoint weighting, namely, the iterated fission probability (IFP) method and the Contribution-Linked eigenvalue sensitivity/Uncertainty estimation via Tracklength importance CHaracterization (CLUTCH) method. The results of the implementation were benchmarked by comparison to MCNP5 calculations, Serpent2 calculations and experimental data in 10 critical configurations. © 2018 International Conference on Physics of reactors, PHYSOR 2018: reactor Physics Paving the Way Towards More Efficient systems. All rights reserved.

关键词： Eigenvalues and eigenfunctions

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Performance comparison of different approximation schemes in matrix MOC

Performance comparison of different approximation schemes in...

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

作者： Yong, Zheng Peng, Minjun Zhou, Yueshan Qiang, Shenglong Ping, An Wei, Lu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Harbin150001 China

ISBN: (纸本)9781713808510

The method of characteristics (MOC) with matrix form has theoretically more favorable features than its standard application, since the time-consuming track sweeping operations are replaced with explicit solution of matrix equation. In traditional MOC, there are three optional discretization strategies: the step characteristic method, diamond difference scheme and linear source approximation. However, their performances in matrix MOC have not be reported so far. The current paper develops their matrix forms and solves the resulted linear systems using preconditioned generalized minimal residual (PGM-RES) method. Additionally, their performances with respect of computation accuracy and efficiency are compared with each other, by simulating a homogeneous hexagonal cell problem and the 2D C5G7 benchmark. The results show that their performances in matrix form are different from that of traditional form. With the same angular quadrature and region partition scheme, the step characteristic method is more efficient significantly than the diamond difference scheme and linear source approximation. Whether the diamond difference scheme and linear source approximation can improve the calculation accuracy or not depends on whether the the spatial mesh is fine enough for every scheme. For the coarser spatial partition strategy, diamond difference scheme and linear source approximation can significantly improve the accuracy of local pin power. © 2018 International Conference on Physics of reactors, PHYSOR 2018: reactor Physics Paving the Way Towards More Efficient systems. All rights reserved.

关键词： Diamonds

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Lattice Boltzmann method for simulation of time-dependent neutral particle transport

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Nuclear science and Techniques 2017年第3期28卷 74-84页

作者： Ya-Hui Wang Li-Ming Yan Bang-Yang Xia Yu Ma School of Energy Science and Engineering Harbin Institute of Technology Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China

In this paper, a novel model is proposed to investigate the neutron transport in scattering and absorbing medium. This solution to the linear Boltzmann equation is expanded from the idea of lattice Boltzmann method(LBM) with the collision and streaming process. The theoretical derivation of lattice Boltzmann model for transient neutron transport problem is proposed for the first *** fully implicit backward difference scheme is used to ensure the numerical stability, and relaxation time and equilibrium particle distribution function are obtained. To validate the new lattice Boltzmann model, the LBM formulation is tested for a homogenous media with different sources, and both transient and steady-state LBM results get a good agreement with the benchmark solutions.

关键词： Transient neutron transport Lattice Boltzmann method Linear Boltzmann equation

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Study on optimization design for CSR1000 core

Study on optimization design for CSR1000 core

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作者： Wang, Lianjie Yang, Ping Lu, Di Zhao, Wenbo Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No. 328 Section 1 Changshun Avenue Shuangliu County Chengdu610213 China

An optimization design of China supercritical water-cooled reactor (SCWR) with the rated electric power of 1000 MWe (CSR1000) conceptual core is proposed. Steady-state performance of the proposed core is then studied with the SCWR core steady-state analysis code system SNTA. These key parameters such as burnup performance, reactivity control capability, power distribution, maximum fuel cladding temperature, and maximum linear power density are analyzed. The relative coolant flow rate of the second flow path, which is suited with assembly power, is also presented. The study shows that the refueling cycle of CSR1000 core can be extended effectively under the optimization design. Copyright © 2018 by ASME.

关键词： Water cooled reactors

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RMC/CTF multiphysics solutions to VERA benchmark problem 9

RMC/CTF multiphysics solutions to VERA benchmark problem 9

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2018 Transactions of the American Nuclear Society, ANS 2018

作者： Ma, Yugao Liu, Shichang Luo, Zhen Wang, Kan Yu, Ganglin Huang, Shanfang Department of Engineering Physics Tsinghua University Beijing100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

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