第一壁

聚变堆第一壁TiC涂层材料研究

Study on the First Wall TiC Coated Materials for Fusion Reactor

~（51）V是ITER工程中第一壁材料的候选核素，在强的14MeV中子辐照下长寿命剩余放射性较少，是重要的结构材料，因此它的一些中子核数据是必须的。

Vanadium is a candidate element for the first wall material of ITER project .

HT-7超导托卡马克第一壁硼碳膜的XPS分析

Analysis of a-B / C ∶ H film deposited in HT-7 superconducting tokamak by XPS

HT-7U装置第一壁抗热冲击SiC厚膜涂层研究

Study on thick SiC coatings with thermal shock resistance on the first wall of HT-7U device

其中屏蔽包层模块（第一壁，简称FW）的加工采用热等静压（HIP）和电子束焊接工艺，并要求对每一个模块的所有焊缝进行无损探伤。

The module first walls ( FW ) are fabricated by Hot Isostatic Pressing ( HIP ) and Electron-Beam Welding .

ITER第一壁、偏滤器靶板和壁的热负荷计算

Power Flux Calculation of First Wall , Divertor Plate and Wall of ITER

HT-7U第一壁材料在HT-7装置中的辐照实验研究

Irradiation experiments of plasma facing materials developed for HT-7U in the HT-7 Tokamak

Tokamak第一壁上W/Cu材料的连接和界面应力的研究

At First Sight INTERFACE FRACTURE Research on Connection and Interface Thermal Stress of W / Cu for Plasma Facing Components of Tokamak Unit

HL2A装置的第一壁由石墨构件、Cu偏滤器靶板和AISI304LN不锈钢真空室内壁组成。

The first wall in the HL-2A tokamak consists of the graphite components , the divertor plates made of Cu and the internal surface of the vacuum vessel made of AISI 304L stainless steel .

HL-1M装置第一壁锂-硅复合涂层及其效果

Si-li coating on the first wall in the HL-1M tokmak and effects on plasma performances

利用通用有限元程序ANSYS对中国氦冷固态氚增殖剂实验包层模块（CHHCSBTBM）第一壁进行了稳态热分析。

The steady thermal analysis for the first-wall of CH HCSB TBM module is carried out firstly using the general FE code ANSYS .

用残气谱研究HT-7超导托卡马克第一壁硼碳膜的吸氧性

Studies of Oxygen Absorption of α - B / C : H Films in HT-7 Superconducting Tokamak by Residual Gases Analysis

结果表明，第一壁铍保护板和RAFM钢的最高温度符合热工安全设计要求。

The results show that the maximum temperature of beryllium armor and RAFM steel of first-wall meet the thermal design requirements .

采用数值计算软件对液态金属增殖区LiPb流场和第一壁热-结构等进行了模拟，并对功率转换系统的热效率进行了计算。

The numerical calculation codes are used to simulate LiPb flow fields of breeder zones and thermal-structure of First Wall . The thermal efficiency of the power conversion system is calculated .

近年来的研究工作表明：低活性Fe-Cr-Mn系合金最有希望替代高洁性Fe-Cr-Ni系合金，使用在核反应堆中，用作第一壁结构材料和包壳材料的。

Lately studies showed that the low activation Fe-Cr-Mn type alloys were very likely to substitute the high activation Fe-Cr-Ni type alloys and can be used as first wall and cladding materials in fusion reactors .

在HT7托卡马克等离子体长脉冲放电过程中，作为直接面对等离子体的第一壁&限制器表面的温度变化及其承受的能流密度的计算，对于判断限制器的作用和对等离子体的影响都有非常重要的意义。

It is important to calculate the temperature change and heat flux in the surface of the limiter in HT-7 for analyzing the influence of its function on the plasma during long pulse discharge .

运用零维模型评估了流动液态锂幕帘作为聚变实验增殖堆工程概要设计（FEB-E）第一壁对聚变等离子体的影响。得到了锂液帘工作温度对堆芯有效平均等离子体电荷？

A global model assessments of the effects of a flowing lithium curtain on plasma has been performed , which is utilized as the first wall for the engineering outline design of the Fusion Experimental Breeder ( FEB-E ) .

在HL1M装置上新开发出一种第一壁原位锂硅复合涂覆技术。

In situ silicon containing lithium coating ( Si Li coating ), a new wall conditioning method , on the first wall in the HL 1M tokamak has been performed by means of plasma assisted chemical vapor deposition .

聚变第一壁新材料性能研究初步

The preliminary study of the first wall material in fusion device

聚变堆第一壁材料的活化特性研究

The activation property study of first wall of fusion reactor

全超导托卡马克第一壁石墨材料的放气特性研究

Out-Gassing Characteristics of Graphite Used in Experimental Advanced Superconducting Tokamak

聚变堆第一壁保护涂层的制备研究

Studies in Preparation of the Coatings for Fusion First Wall

聚变堆第一壁辐照效应研究

The irradiation effects investigation of first wall for fusion reactors

SiC/SiC复合材料第一壁热工设计

Thermo-mechanical design of sic / sic composite first wall

聚变-裂变混合堆第一壁动态二维热应力计算

A two-dimensional calculations of transient thermal stresses for fusion-fission hybrid reactor first wall

石墨第一壁化学腐蚀的温度特性

Temperature characteristics of chemical erosion of graphite first wall

聚变-裂变混合堆第一壁及包层传热学研究

Heat transfer study for the first wall and blanket of the fusion-fission hybrid reactor

在托卡马克第一壁上中子流量及壁负荷的分布

Neutron wall load distribution and neutron current distribution in the first wall of Tokamak

第一壁泄漏杂质的分布计算

Distribution calculation for impurity leaked from first wall

在决定第一壁发热上，这类中子的核数据是重要的。

The nuclear data for these neutrons are important in determining the first wall heating .