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浏览/检索结果: 共18条，第1-10条 帮助 限定条件 发表日期：2017     已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Formation and recovery of cu precipitates in fe-cu model alloys under varying heat treatment 期刊论文 Physica status solidi a-applications and materials science, 2017, 卷号: 214, 期号: 5, 页码: 4 作者:  Zhu, Te;  Wu, Haibiao;  Cao, Xingzhong;  Jin, Shuoxue;  Zhang, Peng 收藏  |  浏览/下载：31/0  |  提交时间：2019/04/23 Cu precipitates  Defects  Heat treatment  Positron annihilation technique   Formation and recovery of Cu precipitates in Fe-Cu model alloys under varying heat treatment 期刊论文 PHYSICA STATUS SOLIDI A-APPLICATIONS AND MATERIALS SCIENCE, 2017, 卷号: 214, 期号: 5, 页码: 1600785 作者:  Zhang, P;  Wang, BY;  Xiao, AN;  Jin, SX;  Cao, XZ 收藏  |  浏览/下载：30/0  |  提交时间：2019/08/27 Cu precipitates  defects  heat treatment  positron annihilation technique   ALISA project: Large-scale experimental facilities for severe accidents studies in Europe and in China 会议论文 作者:  Miassoedov, A.;  Liao, Y.;  Gaus-Liu, X.;  Journeau, C.;  Cassiaut-Louis, N. 收藏  |  浏览/下载：11/0  |  提交时间：2019/11/26 Experimental activities  Experimental facilities  Experimental platform  Large scale experiments  Large-scale research  Reactor Pressure Vessel  Research organization  Severe accident management   Analysis of reactor direct safety injection tube structure on thermal impact 期刊论文 Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2017, 卷号: 51, 页码: 46-51 作者:  Cao, Fang-Fang;  Jiang, Xing;  Weng, Yu;  Wang, Yan-Yan;  Wang, Hai-Jun 收藏  |  浏览/下载：9/0  |  提交时间：2019/11/26 Comparative experiments  Experimental modeling  Flow resistance characteristic  Heat transfer and flows  Reactor Pressure Vessel  Safety injection  Safety injection model  Venturi   MPS analysis of molten corium jet and structure interaction during nuclear severe accident 会议论文 作者:  Li, Gen;  Zhang, Jun;  Yan, Junjie 收藏  |  浏览/下载：6/0  |  提交时间：2019/11/26 High temperature  Metallic material  Molten Corium  Moving particle semiimplicit method  Oxide materials  Reactor Pressure Vessel  Severe accident  Time dependent   Thermal-stress modeling of AP1000 reactor pressure vessel due to transient pressurized thermal shock 期刊论文 Zhongguo Kexue Jishu Kexue/Scientia Sinica Technologica, 2017, 卷号: 47, 页码: 685-691 作者:  Ma, Ziqi;  Zhang, Hongliang;  He, Peifeng;  Xu, Bin;  Luo, Ying 收藏  |  浏览/下载：11/0  |  提交时间：2019/11/26 AP1000  Elastic -plastic models  Elastic-Plastic  Pressurized thermal shock  Reactor Pressure Vessel  Reliability and safeties  Thermal-stress coupling  Wall-temperature distribution   Numerical comparison of the effect of different lower plenum flow diffusers on the core inlet flow distribution of a PWR with Code_Saturne 会议论文 作者:  Xu, T.;  Min, J.;  Bellet, S.;  Ge, J.;  Tian, W. 收藏  |  浏览/下载：14/0  |  提交时间：2019/11/26 Code_Saturne  Comparative studies  Numerical comparison  PIRT analysis  Reactor designs  Reactor Pressure Vessel  Thermal-hydraulic phenomena  Typical structures   Investigation of transient flow and heat transfer for passive nuclear reactor direct safety injection 会议论文 作者:  Weng, Yu;  Liu, Lang;  Jiang, Yang;  Gu, Hongfang;  Wang, Haijun 收藏  |  浏览/下载：2/0  |  提交时间：2019/11/26 Computational fluid dynamics methods  Correlation degree  Direct vessel injection systems  Heat distribution  Radiation surveillance  Reactor internals  Reactor Pressure Vessel  Reactor safety analysis   The primary reactor coolant system concept of the integral, inherently-safe light water reactor 期刊论文 ANNALS OF NUCLEAR ENERGY, 2017, 卷号: 100, 页码: 53-67 作者:  Memmott, Matthew J.;  Manera, Annalisa;  Boyack, Jonathan;  Pacheco, Seth;  Wang, Mingjun 收藏  |  浏览/下载：4/0  |  提交时间：2019/11/26 Integral reactors  (IS)-S-2-LWR  Reactor pressure vessel  SMRs   Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method 期刊论文 ANNALS OF NUCLEAR ENERGY, 2017, 卷号: 104, 页码: 178-190 作者:  Chen, Ronghua;  Tian, Maolin;  Chen, Sen;  Tian, Wenxi;  Su, G. H. 收藏  |  浏览/下载：4/0  |  提交时间：2019/11/26 Computational fluid dynamics  SGTR  Porous media  Thermal-hydraulic analysis  Reactor pressure vessel