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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是321-330 订阅
排序:
Intra Fast Mode Decision Algorithm and Hardware design for AVS2
Intra Fast Mode Decision Algorithm and Hardware Design for A...
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2021 International Conference on Signal Processing and Machine Learning (CONF-SPML)
作者: Hao Xie Kaiyang Liu Yang Zhao Xiao Zheng Xianguo Qing Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China School of Software and Microelectronics Peking University
AVS2 is a kind of video coding standard proposed by China,it adopts 33 intra prediction modes to improve coding performance,while the computational complexity has increased *** order to reduce the complexity of AVS2 i... 详细信息
来源: 评论
High-Fidelity Neutronic/Thermal-Hydraulic Coupling Analysis of Plate-Type reactor based on MOOSE and cosRMC
SSRN
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SSRN 2023年
作者: Chen, Junyi Liu, Guodong Huang, Shanfang He, Ying Qiu, Meiming Wang, Kan Lu, Chuan Li, Zhigang Quan, Guoping Wang, Xing Department of Engineering Physics Tsinghua University Haidian district Beijing100084 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Shuangliu district Chengdu610213 China State Power Investment Corporation Research Institute Changping district Beijing102209 China
A full scale high-fidelity neutronic/thermal-hydraulic coupled analysis method for plate-type reactor is proposed based on the open-source Multiphysics Object-Oriented Simulation Environment (MOOSE) and Monte Carlo Co... 详细信息
来源: 评论
Study on irradiation damage of rpv steels based on coupling cluster dynamics and crystal plasticity finite element method
Study on irradiation damage of rpv steels based on coupling ...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Wang, Xiaotong Luo, Ying Dong, Yuanyuan Yao, Weihua Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China
Irradiation hardening is one of the most important aging effects of reactor pressure vessel (RPV) steel in long-term service. A number of studies have indicated that irradiation hardening is mainly caused by irradiati... 详细信息
来源: 评论
Burnup performance analysis for candidate materials of the LWR accident tolerant control rod  14
Burnup performance analysis for candidate materials of the L...
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14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019
作者: Liu, Yong Li, Mancang Yu, Yingrui Xiao, Peng Wang, Xingbo Zhang, Bin Wang, Dongyong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China 328# Section 1 Changshun Avenue Chengdu China
The accident tolerant fuel (ATF) is considered to be one of the most advanced concepts to improve the safety of light water reactors (LWRs). The accident tolerant control rod (ATCR) is a significant aspect in the ATF ... 详细信息
来源: 评论
DC-Side Decoupling Method of DC-link Capacitor Reduction for Single Phase PWM Rectifier
DC-Side Decoupling Method of DC-link Capacitor Reduction for...
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2020 IEEE Sustainable Power and Energy Conference, iSPEC 2020
作者: Wang, Jinxin Renyong, Peng Dai, Kailei Zhang, Zhiqiang Zhang, Ting Zhao, Junjie Chen, Qian Zhang, Jianjian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China
The integrated charging system of Electric vehicle consists of a single-phase PWM rectifier and a Buck converter. When the single-phase PWM rectifier works with unit power factor, the dc-link voltage contains a large ... 详细信息
来源: 评论
Study on the thermal-mechanical performance of SiC composites cladding under multiple conditions
Study on the thermal-mechanical performance of SiC composite...
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2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
作者: Yin, Chunyu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No.328 section 1 changshun avenue Chengdu China
SiC has become a candidate cladding material of Accident Tolerant Fuels (ATF) due to its excellent irradiation stability and corrosion resistance. However, because SiC is a ceramic material with low toughness, brittle... 详细信息
来源: 评论
Effect of residual pore on the performance of UN kernel TRISO particle fuel  14
Effect of residual pore on the performance of UN kernel TRIS...
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14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019
作者: Liu, Shichao Chen, Ping Zhou, Yi Pang, Hua Xi, Yong Tang, Changbing Zhao, Yanli Qiu, Xi Guo, Zixuan Nuclear power institute of China Science and Technology on Reactor System Design Technology Laboratory Changshun Stress No.1 Chengdu Sichuan610200 China
The thermal-mechanical performance of uranium nitride (UN) tri-isotropic (TRISO) particle with residual pore used in Light Water reactor (LWR) was investigated. The effect of pore size and location on the performance ... 详细信息
来源: 评论
Simulation of Nuclear reactor Accident Scenarios using Physics-Informed Neural Networks and Transfer-Learning
Simulation of Nuclear Reactor Accident Scenarios using Physi...
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Electronic Information Engineering and Computer science (EIECS), 2021 International Conference on
作者: Yang Yu Yufei Xie Wenlin Wang Guohua Wu Haitao Lan Enbo Lin Ping An Zibin Sun Haichuan Zhang Yixian Wu National Key Laboratory of Parallel and Distributed Computing National University of Defense Technology Changsha China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China School of Automation Wuhan University of Technology Wuhan China Sino-German College of Intelligent Manufacturing Shenzhen Technology University Shenzhen China Institute of Automotive Engineers Hubei University of Automotive Technology Shiyan China Nuclear Power Institute of China Chengdu China
In a Loss of Coolant Accident (LOCA), reactor core temperatures can rise rapidly, leading to potential fuel damage and radioactive material release. This research presents a groundbreaking method that combines the pow... 详细信息
来源: 评论
Corrosion Behavior of Micro-Arc Oxidation Coating on Zirconium Alloy in Superheated Steam Condition
SSRN
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SSRN 2022年
作者: Li, Zheng-Yang Zheng, Mei-Yin Yang, Zhong-Bo Ren, Quan-Yao Cai, Zhen-Bing Jiao, Yong-Jun Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Tribology Research Institute Key Lab of Advanced Technologies of Materials Southwest Jiaotong University Chengdu610031 China
The corrosion behavior of MAO coating on Zr alloy was investigated in 400 ºC/10.3 MPa condition. The surface morphology, phase composition, and element distribution of MAO coating were analyzed. The results indic... 详细信息
来源: 评论
Facility Layout in Horizontal Cylindrical Space Based on Adaptive Gradient Descent Algorithm
Facility Layout in Horizontal Cylindrical Space Based on Ada...
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第40届中国控制会议
作者: Peng Yuan Yiran Miao Deqing Huang Junkai Hao Na Qin School of Electrical Engineering Southwest Jiaotong University Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China
FLP(Facility layout problem) is a common problem in engineering field. The past research tend to focus on the twodimensional space and a small amount of three-dimensional box space as well as vertical cylinder space... 详细信息
来源: 评论