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检索条件"机构=Science and Technology on Reactor System Design"
626 条 记 录,以下是241-250 订阅
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Research on the influence of ocean condition on the oscillation in parallel double-channel
Research on the influence of ocean condition on the oscillat...
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18th International Conference on Nuclear Engineering, ICONE18
作者: Zhou, Linglan Hong, Zhang Department of Physic Engineering Tsinghua University China National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute Of China China
In this paper, the flow oscillation in the parallel multichannel system has been studied under ocean condition with RELAP5/MC. A double-channel boiling system model is built using the code RELAP5/MC and it is proved t... 详细信息
来源: 评论
Research on trans critical characteristic on sliding pressure booting process of SCWR
Research on trans critical characteristic on sliding pressur...
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2013 21st International Conference on Nuclear Engineering, ICONE 2013
作者: Liu, Liang Zhou, Tao Song, Mingqiang Chen, Juan Luo, Feng Xia, Bangyang North China Electric Power University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
The homogeneous flow model of trans critical transient calculation is achieved by the trans critical program of SCWR which is made by FORTRAN. The SCWR sliding pressure starting scheme is simulated by this program. So... 详细信息
来源: 评论
Preliminary analysis of FCM fuel thermal-mechanical performance under normal and transient conditions
Preliminary analysis of FCM fuel thermal-mechanical performa...
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Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance
作者: Li, Wenjie Tang, Changbing Liu, Zhenhai Li, Wei Chen, Ping Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Design Sub-institute Nuclear Power Institute of China Chengdu610213 China
FCM fuel is a candidate fuel form to replace commercial UO2 fuel rod in LWR to enhance fuel reliability under accident conditions. The FCM pellet consists of TRISO particles embedded inside the dense SiC matrix. This ... 详细信息
来源: 评论
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 2021
作者: Xie, Hao Liu, Kaiyang Zhao, Yang Zheng, Xiao Qing, Xianguo Nuclear Power Institute of China Science and Technology on Reactor System Design Technology Laboratory Chengdu China Peking University School of Software and Microelectronics Beijing China
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 dramatically. In order to reduce the compl... 详细信息
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Calculation strategy for the determination of plasticity correction factors  13th
Calculation strategy for the determination of plasticity cor...
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13th Asia-Pacific Symposium on Engineering Plasticity and its Applications, AEPA 2016
作者: Du, Juan Shao, Xue Jiao Kan, Qian Hua Zhang, Ying Fu, Xiao Long Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610041 China Southwest Jiaotong University Chengdu610031 China
This paper presents an investigation about the plasticity correction factor, Ke, proposed in the RCC-M code, for the correction of elastic stress range exceeds twice the yield stress which results from both mechanical... 详细信息
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Fuel assembly design for supercritical water-cooled reactor
Fuel assembly design for supercritical water-cooled reactor
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作者: Linna, Feng Fawen, Zhu Science and Technology on Reactor System Design Technology Laboratory Third Section of Huafu Road Huayang Town Shuangliu County Chengdu Sichuan Province610213 China
The supercritical water-cooled reactor (SWCR) has been selected as one of the most promising reactors for Generation IV nuclear reactors due to its higher thermal efficiency and more simplified structure compared to t... 详细信息
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Modification of severe accident analysis code for accident tolerant fuel (ATF) applications  27
Modification of severe accident analysis code for accident t...
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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019
作者: Xu, Tao Ma, Haifu Tian, Chao Wu, Yirui Yang, Junyun Wang, Kai Zhang, Bin Wang, Junlong Deng, Yaxin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi China
After the Fukushima nuclear accident, we gradually realized the safety issues of the traditional UO2+Zr nuclear fuel system. Accident tolerance fuel (ATF) is a new generation fuel concept proposed to improve the perfo... 详细信息
来源: 评论
Numerical study on single Droplet's rise in steam separator by using VOF method
Numerical study on single Droplet's rise in steam separator ...
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2014 ANS Winter Meeting and Nuclear technology Expo
作者: Zhang, Di Luo, Qi Huang, Wei Wang, Kan Department of Engineering Physics Tsinghua University Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
来源: 评论
Development and Verification of a New Depletion, Activation and Radiation Source Term Calculation Code  23rd
Development and Verification of a New Depletion, Activation ...
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23rd Pacific Basin Nuclear Conference, PBNC 2022
作者: Wen, Xingjian Zhai, Zian Tang, Songqian Tian, Chao Liu, Zhouyu Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China Xi’an Jiaotong University Xi’anShaanxi China
Existing depletion and source term calculation codes lack flexible interfaces, which is difficult to meet the actual engineering design needs. Based on the Chebyshev rational approximation method, a new depletion, act... 详细信息
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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
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 th... 详细信息
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