可溶液加工有机/无机纳米复合发光器件

来源 :2016年全国光机电技术及系统学术会议暨中国光学学会光电技术专委会/中国仪器仪表学会光机电分会会员代表大会 | 被引量 : 0次 | 上传用户：chiyulong2000

【摘要】

：

随着显示产业的发展，对于器件柔性化的需求开始受到包括学术界和产业界的广泛重视。柔性显示器件通常采用塑料等可挠曲基板材料，因此对于器件的制作温度有明确的限制，不能采用传统的高温制程。溶液加工技术，包括常用的旋转旋涂，刮涂，以及近年来受到关注的印刷技术，就成为柔性显示器件制作的首选方案。

【作者】

：

李福山

【机构】

：

福州大学

【出处】

：

2016年全国光机电技术及系统学术会议暨中国光学学会光电技术专委会/中国仪器仪表学会光机电分会会员代表大会

【发表日期】

：

2016年3期

下载到本地 , 更方便阅读

下载此文赞助VIP

声明 : 本文档内容版权归属内容提供方 , 如果您对本文有版权争议 , 可与客服联系进行内容授权或下架

论文部分内容阅读

其他文献

The influences of irradiation defects on mechanical properties for ceramic breeder material Li2TiO3

Tritium breeder materials are significant for blanket design of fusion reactor.However,during blanket operation,the ceramic breeder materials will be subjected to neutron irradiation which could be de

会议

Li2TiO3mechanical propertiesdeuterium irradiationdefect

Synergistic effect of ion irradiation and lithium corrosion on the microstructure and mechanical pro

Vanadium alloy is considered as the first candidate material for self-cooled lithium blanket for its excellent neutron resistance、mechanical property and compatibility with lithium.In the real applica

会议

ion irradiationLi corrosionV-4Cr-4Ti

Microstructural and properties change of W-Sc2O3/ZrC composites under helium irradiation

W-ZrC composites reinforced with Sc2O3 particles were produced through powder metallurgy(PM)and subsequent spark plasma sintering(SPS)at 1700 °C and 13.7 KN.The microstructure and properties of the co

会议

W-Sc2O3/ZrC compositesSpark plasma sinteringHelium irradiationMicro hardness

Bi-Directional hydrogen isotopes permeation through a reduced activation ferritic steel alloy F82H

Reduced activation ferritic steel alloys such as F82H are the candidate materials for the first wall of DEMO reactors.For self-cooled breeding blankets,the first wall will be subjected to bi-direction

会议

Bi-Directional hydrogen isotopes permeationF82HPDPGDP

Research on the damage behavior of lutecium doped W-based material exposed to repetitive high heat f

The transient thermal shock performances and relevant damage mechanism of pure W and lutecium doped W alloys were investigated via a repetitive laser beam heat load test to simulate the transient heat

会议

Transient thermal shock testLaser beamLutecium doped W-based materialMechanis

The effect of the ion beam energy on the mechanical properties and microstructural of the W-3wt%Lu2O

W-3wt%Lu2O3 composites were prepared by mechanical milling and spark plasma sintering.The W-3wt%Lu2O3 composites were maintained in a vacuum at room temperature,and irradiated with a He+(He+ion beam f

会议

W-Lu2O3 compositesHe+irradiationFuzzHe bubblesPoly crystallizationAmorphiza

Effect of dislocation on helium retention in deformed 316L stainless steel

Austenitic stainless steels 316L have been widely utilized for industrial application,especially,as the candidate structural materials for fusion reactor.It is well known that helium atoms can be trap

会议

DislocationHelium defect clustersThermal desorptionPositron annihilationDeso

Microstructure of beryllium with argon ion irradiation

Beryllium is planned to be used as a neutron multiplier in the Helium-cooled ceramic breeder(HCCB)test blanket module(TBM)which is the primary option of the Chinese TBM program.The character of the mi

会议

BerylliumIrradiation damageMicrostructure

Electron microscopy study of 10 keV He+irradiated W/W-Alloys

Tungsten-based materials form a prime candidate of plasma facing components in fusion power reactors,and are subject to substantial amount of radiation damage from the bombardments of fast neutrons,as

会议

W/W-alloysHeliumRadiation damage

ACPs source analysis of different materials in Water-Cooled loops of fusion reactor with CATE progra

The source term caused by activated corrosion products(ACPs)is an important radiation hazard in water-cooled fusion reactor,which directly determines the occupational radiation exposure during operati

会议

Activated corrosion productsFusion reactorSource termMaterial selectionCATE

可溶液加工有机/无机纳米复合发光器件

其他学术论文