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DEVELOPMENT OF CARBON COMPOSITE MATERIALS HIGHLY RESISTANT TO RADIATION DAMAGE

高抗辐射损伤碳复合材料的开发

基本信息

批准号：
07555485
负责人：
OKU Tatsuo
金额：
$ 0.58万
依托单位：
IBARAKI UNIVERSITY
依托单位国家：
日本
项目类别：
Grant-in-Aid for Scientific Research (B)
财政年份：
1995
资助国家：
日本
起止时间：
1995 至 1996
项目状态：
已结题

来源：
https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-07555485/
关键词：
fusion plasma facing component carbon fiber neutron irradiation ion irradiation microstructure radiation damage effect caobon composite material tensile properties 微細構造照射損傷寸法変化力学特性

项目摘要

Carbon composite materials which have higher thermal conductivity at high temperature irradiation are desirable in order to improve erosion resistant properties of those materials at high temperatures for plasma facing components of fusion devices or fusion reactors. Carbon composite materials are composed of carbon fibers and carbon matrices and in general the degree of crystallinity of carbon fibers is lower than that of carbon matrices. Since irradiation effects of carbon materials having low degree of crystallinity are normally larger than those of high crystalline materials, it is important to use higher stable carbon fibers to radiation damage to get carbon composite materials having higher resistance to radiation damage. On the basis of this idea, various carbon fibers which have different fine structures were prepared and neutron irradiation effects on the dimension, mechanical strength and etc.of those fibers were examined. Nine kinds of carbon fibers were used : four kinds of … More mesophase pitch fibers having different fine structures, two kinds of pitch carbon fibers and three kinds of PAN fibers. Neutron irradiation has been performed using JMTR at 150-180ﾟC up to (2.0-2.7) x1024n/m2 (E>0.18Me). As a result, the notch angle of a carbon fiber of radially notched structures decreased. This is considered to be reflected by the result of expansion of c-direction due to irradiation. The diameter of most carbon fibers increased but some fibers decreased. Change of heat-treated materials due to irradiation was smaller than that of the original materials. Tensile strengths of almost all fibers except one decreased. The reason for this is considered that some cracks are produced in the fiber and some fibers break in the axial direction. Argon ion of 175MeV-1muA was irradiated to carbon fibers by using AVF cyclotron for 400 and 200 min. After ion irradiation the dimension of the cross section and tensile test were performed. As a result, surface damages were large, the diameter of the cross section decreased and the tensile strength increased.If we review the results above, the C/C composite materials which are made of the mesophase pitch fiber with radial notch or pitch fiber are recommended because of radiation damage-resistant properties. A trial product of C/C composite which is made of pitch fiber was exposed to ion and neutron irradiations and the radiation damage-resistant properties is to be examined and confirmed by after irradiations tests in the future. Less

期望在高温辐射下具有更高导热率的碳复合材料，以改善这些材料在高温下对于聚变装置或聚变反应堆的面向等离子体的部件的耐腐蚀性能。碳复合材料由碳纤维和碳基体组成，通常碳纤维的结晶度低于碳基体。由于结晶度低的碳材料的辐射效应通常大于结晶度高的碳材料的辐射效应，因此重要的是使用对辐射损伤更稳定的碳纤维，以获得具有更高耐辐射损伤性的碳复合材料。在此基础上，制备了具有不同精细结构的各种碳纤维，并考察了中子辐照对这些纤维的尺寸、机械强度等的影响。使用了九种碳纤维：四种 ...更多信息具有不同精细结构的中间相沥青纤维、两种沥青碳纤维和三种PAN纤维。用JMTR在150-180 ℃下进行了中子辐照，辐照剂量高达（2.0-2.7）× 10 ~（24）n/m ~ 2（E>0.18Me）。结果，径向切口结构的碳纤维的切口角减小。这被认为是由照射引起的c方向的扩展的结果所反映的。大部分碳纤维直径增大，但也有部分纤维直径减小。热处理后材料辐照后的变化小于原始材料。除一种纤维外，几乎所有纤维的抗张强度均下降。其原因被认为是在纤维中产生一些裂纹并且一些纤维在轴向方向上断裂。用AVF回旋加速器对碳纤维进行了175 MeV-1 μ A氩离子辐照400和200 min，并对辐照后的碳纤维进行了截面尺寸测量和拉伸试验。综合以上结果，以中间相沥青纤维或沥青纤维为基体的C/C复合材料具有较好的抗辐射损伤性能，是目前推荐使用的C/C复合材料。以沥青纤维为原料制备的C/C复合材料试件进行了离子辐照和中子辐照试验，其抗辐照损伤性能有待于后续辐照试验的检验和验证。少