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2019 Transactions of the American Nuclear Society, ANS 2019

作者： Wang, Yaqi Gaston, Derek Lindsay, Alexander Laboure, Vincent Nuclear Methods Development Idaho National Laboratory Idaho FallsID United States Nuclear Science and Technology Modeling and Simulation Idaho National Laboratory Idaho FallsID United States Reactor Physics Analysis and Design Idaho National Laboratory Idaho FallsID United States

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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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How might a collapse in the Atlantic Meridional Overturning Circulation affect rainfall over tropical South America?

Climate Resilience and Sustainability

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Climate Resilience and Sustainability 2022年第1期1卷

作者： Good, Peter Boers, Niklas Boulton, Chris A. Lowe, Jason A. Richter, Ingo MetOffice Hadley Centre Exeter United Kingdom Earth System Modelling School of Engineering and Design Technical University of Munich Munich Germany Potsdam Institute for Climate Impact Research Potsdam Germany Global Systems Institute and Department of Mathematics University of Exeter Exeter United Kingdom Priestley International Centre for Climate University of Leeds Leeds United Kingdom Application Laboratory Research Institute for Value-Added-Information Generation Japan Agency for Marine-Earth Science and Technology Yokohama Japan

The seasonal response of rainfall over tropical South America to a shutdown in the Atlantic Meridional Overturning Circulation (AMOC) is examined, in HadGEM3 model simulations where freshwater is added to the north Atlantic. Potential biases in these simulations are explored by comparing the unperturbed simulation with observations. In this simulation, in years when the latitude of the model Atlantic Intertropical Convergence Zone (ITCZ) is realistic, the model provides a reasonable simulation of the spatial and seasonal variation in regional-scale rainfall over tropical South America. However, some climatological mean rainfall biases over this region are attributed to the climatological southward bias in the Atlantic ITCZ. Under an AMOC shutdown, the rainfall changes over tropical South America are largely associated with a southward shift of the Atlantic ITCZ. The large seasonal variation in rainfall change over tropical South America is linked primarily with the variation in the location of peak rainfall (itself driven largely by variation in the latitude of peak solar insolation and by the lagged variation in Atlantic ITCZ). The simulated rainfall changes appear to be biased in some months by the southward bias in the Atlantic ITCZ, including a possible overestimation of drying in March and June. In addition, the Atlantic ITCZ in HadGEM3 tends to shift too far in both the seasonal cycle (as reported in other models) and in inter-annual variability. Excessive inter-annual variability may arise because the model ITCZ is too close to the equator, combined with an increase in variability near the equator. Further understanding of what drives the variability in ITCZ latitude, and how that relates to ITCZ shifts under an AMOC shutdown, is suggested as a future research priority. © 2021 The Authors. Climate Resilience and Sustainability published by John Wiley & Sons Ltd on behalf of Royal Meteorological Society.

关键词： geographic/climatic zone geophysical sphere physical phenomenon scale tools and methods

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Unified Rendering Array Driver Runtime Optimization for Graphic Application 6

Unified Rendering Array Driver Runtime Optimization for Grap...

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6th Annual 2018 International Conference on Geo-Spatial Knowledge and Intelligence, GSKI 2018

作者： Ma, Chengcheng Tian, Ze Liu, Honghong Nie, Zhao China Aeronautical Computing Research Institute China Aviation Key Laboratory of Science and Technology on Integrated Circuit and Micro-System Design P.O. Box 710068 China Xiangteng Microelectronics Technology Co. LTD P.O. Box 710068 China

As the core of GPU processing, the performance of Unified rendering array is directly affected by the shader driver. On the basis of research the structure of Unified rendering array processing, this paper proposes a runtime Unified rendering array driver optimization method for graphical application, can according to different graphics application scenario runtime to generate optimized Unified rendering array driver, testing on graphics processors FPGA verification environment, driven by the runtime optimization compared with the traditional full function driver, performance increased by 55% - 270%. © Published under licence by IOP Publishing Ltd.

关键词： Array processing

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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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Methods and Verification of 3D direct reactor calculation code KYCORE

Methods and Verification of 3D direct reactor calculation co...

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

作者： Tang, Xiao Li, Qing Chai, Xiaoming Tu, Xiaolan Peng, Xingjie Wang, Kan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Department of Engineering Physics Tsinghua University Beijing 100084 China

ISBN: (纸本)9781713808510

KYCORE is a 3D direct reactor calculation code capable of performing reactor hetero geneous calculation without cross section homogenization and group condense. It is developed in Nuclear Power Institute of China, involving radial characteristics method (MOC) and axial discrete ordinate method (SN) coupled 3D neutron transport and subgroup method with fixed source problem for resonance treatment and depletion, aiming at providing mini core design and commercial reactor benchmark solution. This article briefly introduces optimized MOC/SN coupling, adjusted coarse mesh finite difference (CMFD) and resonance treatment. The accuracy of the code is verified with 3D VERA Problem 3 benchmark and proves to be credible. © 2018 International Conference on Physics of reactors, PHYSOR 2018: reactor Physics Paving the Way Towards More Efficient systems. All rights reserved.

关键词： Codes (symbols)

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Development of a sensitivity analysis code for 3-D C5G7 benchmarks based on the pertubation theary

Development of a sensitivity analysis code for 3-D C5G7 benc...

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

作者： Wu, Qu Peng, Xingjie Yu, Yingrui Li, Qing Wang, Kan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Department of Engineering Physics Tsinghua University Beijing100084 China

ISBN: (纸本)9781713808510

Sensitivity and Uncertainty (S&U) analysis plays a major role in reactor physics. Uncertainty in reactor engineering comes from model error, numerical error and input parameter error. Nuclear data are regarded as crucial input parameters and proven to be a major uncertainty source. Therefore, effective evaluation of nuclear data can promote the accuracy and fidelity of nuclear system simulation. In deterministic codes, however, most studies about S&U analysis are based on the traditional two-step method, i.e. assembly calculation and core simulation. With the development of advanced 2-D/l-D transport codes, the corresponding S&U analysis model is required. A new S&U analysis code, namely KYADJ, achieved the sensitivity analysis of eigenvalue with respect to material macroscopic cross sections based on classical perturbation theory. Forward and adjoint flux were solved by the coupling of 2-D Method of Characteristics (MOC) and 1-D discrete ordinates method (Sn). Besides, the Direct Numerical Perturbation (DNP) method in KYADJ and the Iterated Fission Probability (UP) method in reactor Monte Carlo code (RMC) were adopted to calculate sensitivity coefficients for comparison. A 3x3 pin-cell benchmark and 3-D OECD/NEA C5G7 benchmarks were applied to verify the ability of sensitivity analysis in KYADJ. Results showed that a good agreement among three approaches was achieved. KYADJ can accurately calculate eigenvalue sensitivity coefficients with respect to input nuclear data. © 2018 International Conference on Physics of reactors, PHYSOR 2018: reactor Physics Paving the Way Towards More Efficient systems. All rights reserved.

关键词： Sensitivity analysis

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Numerical simulation research on the performance of SCWR fuel rod

Numerical simulation research on the performance of SCWR fue...

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作者： Tang, Changbing Xing, Shuo Pang, Hua Chen, Ping Zhou, Yi Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No. 328 First Section of Changshun Avenue Shuangliu District Sichuan610041 China

Because of the high temperature and high pressure characteristics of supercritical water-cooled reactor (SCWR), the thermal hydraulic performance of SCWR is greatly different from pressurized water reactor (PWR), which makes the current PWR fuel rod performance analysis codes are no longer applicable to SCWR. In this research, the irradiation swelling, irradiation densification, thermal expansion, thermal creep, plastic deformation, irradiation creep and irradiation hardening of UO2 pellet, and stainless steel cladding were considered;the gas conductance and radiant conductance of gap heat transfer were considered, the forced convective heat transfer on the outer surface of cladding was considered. Meanwhile, the irradiation effects and the thermal effects on the materials parameters such as thermal conductivity, specific heat, and young’s modulus were also considered in this research. With the help of ABAQUS software, the related user-defined subroutines were developed, and the irradiation effects and thermal effects of SCWR fuel were introduced into the numerical simulation, and then completed the analysis of SCWR fuel rods’ performance under steady power conditions. Some reference suggestions for the design and development of SCWR fuel could be provided by the establishment of this numerical simulation method. Copyright © 2018 by ASME.

关键词： Pressurized water reactors

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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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