ZIRCALOY

作品数:15被引量:10H指数:2
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相关作者:姚美意周邦新吴璐温榜何文更多>>
相关机构:重庆大学中国科学技术大学上海大学中国核动力研究设计院更多>>
相关期刊:《Acta Metallurgica Sinica(English Letters)》《Acta Mechanica Sinica》《Science China(Technological Sciences)》《Journal of Wuhan University of Technology(Materials Science)》更多>>
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Direct FE^(2)multiscale simulation of hydrogen diffusion in Zircaloy cladding
《Acta Mechanica Sinica》2024年第12期1-14,共14页Han Zhao Xianghua Zheng Shiting Yang Xin Yang Wei Li 
supported by the National Natural Science Foundation of China(Grant No.52301131);Natural Science Foundation of Sichuan,China(Grant No.2023NSFSC0908);Research Foundation for Talents of Chengdu Technological University(Grant No.2023RC017).
This study utilizes Direct FE^(2) multiscale simulation techniques to propose an innovative approach for analyzing hydrogen diffusion in Zircaloy cladding.This method combines finite element simulations at two scales ...
关键词:Direct FE^(2) Zircaloy cladding Hydrogen diffusion Voids 
Zirconium Metal Recovery from Zircaloy in Molten Fluorides
《Materials Sciences and Applications》2024年第12期559-571,共13页Laurent Massot Mathieu Gibilaro Delphine Quaranta Jerome Serp Pierre Chamelot 
This article focuses on the electrorefining process in molten fluorides to selectively recover zirconium from one Zr-based metallic alloy involved in the field of nuclear energy: Zircaloy-4. Firstly, zirconium electro...
关键词:Molten Fluorides ZIRCONIUM ZIRCALOY-4 ELECTROREFINING Dissolution Pathway 
锆合金包壳材料堆内行为的研究进展被引量:5
《材料科学》2019年第9期861-871,共11页潘荣剑 汤爱涛 吴璐 何文 王海东 温榜 伍晓勇 
国家自然科学基金资助项目(51601185);国防基础科研计划资助(JCKY2017201C016);国家重点研发计划资助项目(2016YFB07001);中国先进核电标准体系研究(第二阶段,2017ZX06004001)。
目前使用最广泛和成熟的压水堆包壳材料是Zircaloy-2和Zircaloy-4。然而随着核动力反应堆技术朝着提高燃料燃耗和降低燃料循环成本、提高反应堆热效率和提高安全可靠性的方向发展,对关键核心部件燃料元件包壳材料锆合金的性能提出了更...
关键词:ZIRCALOY 析氢 氧化 辐照蠕变 性能退降 
Texture Evolution and Ultrafine Grain Formation in Cross-Cryo-Rolled Zircaloy-2
《Acta Metallurgica Sinica(English Letters)》2015年第7期837-846,共10页Sunkulp Goel R.Jayaganthan I.V.Singh D.Srivastava G.K.Dey N.Saibaba 
BRNS,Bombay for their financial grant to this work (No.BRN-577-MMD)
The texture and mechanical properties of cross-rolled zircaloy-2 at 77 and 300 K were investigated.Crossrolling at 77 K was performed to impart different thickness reductions of 25% and 50%,while at 300 K with 25%,50%...
关键词:Cross-rolling EBSD TEM Ultrafine grains Texture 
Properties of passive nano films on zircaloy-4 affected by defects induced by hydrogen permeation
《Chinese Physics B》2014年第8期154-159,共6页顾俊骥 凌云汉 张瑞谦 戴训 白新德 
Project supported by the National Basic Research Program of China(Grant No.2011CB610501);the Funds from the State Key Laboratory of Surface and Chemistry,China(Grant No.SPC 201102);the Reactor Fuel and Materials Laboratory,China(Grant No.STRFML-2013-05)
In this work, hydrogen absorption and the permeation behavior of the passive layer formed on zircaloy-4 are in- vestigated. Potentiodynamic polarization, Mott-Schottky analysis, electrochemical impedance spectroscopy,...
关键词:ZIRCALOY DEFECTS hydrogen permeation electrochemical measurement 
Preliminary Developments of Miniplate-Type Fuel of U-2.5Zr-7.5Nb Alloy Dispersed and Cladded in Zircaloy
《Journal of Energy and Power Engineering》2014年第8期1409-1414,共6页Natalia Mattar Cantagalli Kelly Cristina Martins Faeda Rafael Witter Dias Pais Ana Maria Matildes dos Santos Wilmar Barbosa Ferraz 
Nuclear fuel based on uranium metal alloys is utilized in research and test reactors. For the purpose of the reduction of fuel enrichment, high densities of uranium-235 in this kind of fuel are needed. This can be ach...
关键词:Nuclear fuel plate U-Zr-Nb alloy Zry 
Revisiting Stainless Steel as PWR Fuel Rod Cladding after Fukushima Daiichi Accident
《Journal of Energy and Power Engineering》2014年第6期973-980,共8页Alfredo Abe Claudia Giovedi Daniel de Souza Gomes Antonio Teixeira e Silva 
In the past, stainless steel was utilized as cladding in many PWRs (pressurized water reactors), and its performance under irradiation was excellent. However, stainless steel was replaced by zirconium-based alloy as...
关键词:Austenitic stainless steel cladding Zircaloy cladding PWR fuel rod steady-state fuel performance codes. 
锆合金管材加工过程中的织构研究被引量:3
《材料导报(网络版)》2011年第4期4-9,共6页周宇 栾佰峰 贾明星 
以典型材料(Zr-25Nb、ziraloy)为例,总结分析了α+β两相和α单相锆合金管材加工过程中的织构研究情况,重点对其织构特点及形成原因进行了阐述。结果表明,两相区轧制的Zr-2.5Nb管材主要为横向基面织构,这与大量存在的连续β相有...
关键词:锆合金管材 织构 Zr-2.5Nb ZIRCALOY 
Effect of surface nanocrystallization on the corrosion behavior of Zircaloy-4
《Science China(Technological Sciences)》2009年第8期2227-2231,共5页ZHU YuTao1,2 & ZHANG XiYan1,2,3 1 College of Materials Science and Engineering, Chongqing University, Chongqing 400045, China 2 National Engineering Research Center for Magnesium Alloys, Chongqing University, Chongqing 400044, China 3 School of Physical Science and Engineering Technology, Guangxi University, Nanning 530004, China 
Supported by the National Natural Science Foundation of China (Grant No. 50461001);Guangxi Science and Technology Fund (Grant Nos. 0575-18, 0639003);Science Fund of Guangxi University (Grant No. 2005ZD04)
The contrastive corrosion experiments between surface nanocrystallined Zircaloy-4 and coarse-grained Zircaloy-4 under the condition of 673 K/10.3 MPa in pure water are carried out, and the microstructure of oxide film...
关键词:NANOCRYSTALLINE ZIRCALOY OXIDE FILM microstructure 
Effect of heat treatment on the Nb distribution and corrosion resistance of Zr-Sn-Nb-Fe zirconium alloy
《Rare Metals》2008年第2期192-196,共5页LIU Wenqing GENG Xun LIU Qingdong LI Qiang ZHOU Bangxin YAO Meiyi 
This work was financially supported by the National Science Foundation of China (No.50571056);the National Science Foundation of Shanghai (No.04ZR14057).
After being treated in different ways, Zr-Sn-Nb-Fe alloy specimens are exposed in 0.01mol/L LiOH aqueous solution at 350℃ under 16.8 MPa. The examination of microstructures and second phase particles (SPPs) of thes...
关键词:ZIRCALOY heat treatment corrosion resistance MICROSTRUCTURE second phase particles 
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