惯性约束聚变靶材料掺杂技术综述

文章概要综述了惯性约束聚变掺杂靶材料的制备方法，内容包括聚苯乙烯掺卤素和过渡金属元素，玻璃与塑料掺簇粒子，以及塑料涂层掺高Ｚ金属等。简述了掺杂材料的分析测试手段及其在ＩＣＦ中的应用。     

激光惯性约束聚变中的氘,氚核自旋极化方法

介绍了激光惯性约束聚变（ＬＩＣＦ）中的氘（Ｄ）、氚（Ｔ）热核燃料核自旋极化的基本原理，综述了这一课题的进展情况。讨论了动态核极化理论在氘氚（ＤＴ）核极化中的固体效应、自旋温度效应以及速率方程，并说明了在激光惯性约束聚变反应堆研究中采用极化的氘氚热核燃料所带来的利益，提出了今后该课题将继续研究的几个问题。     

惯性约束聚变低温冷冻氘氚靶制备技术

低温冷冻氘氚靶对于惯性约束聚变研究至关重要,主要有塑料微球靶、金属铍球靶、泡沫球壳靶等。根据微球球壳材质的不同,采用不同的低温冷冻氘氚靶制备技术。塑料微球靶采用“高压充氘氚-冷冻法”或“充气管充气法”;金属铍球靶采用“低温、低压冷凝法”或“高温、高压扩散连接半球壳法”;多孔泡沫球壳靶采用“球壳材料吸附氘氚液体法”。本文简述上述技术和方法的发展状况和趋势。     

气凝胶的制备及其在惯性约束聚变实验中的应用

气凝胶是惯性约束聚变(ICF)实验中的一种理想的靶材料.文章介绍SiO2气凝胶、有机和碳气凝胶、二元气凝胶、掺杂SiO2气凝胶和其它几种气凝胶的研制,探讨了气凝胶在ICF相关研究领域的应用.     

惯性约束聚变实验中全程控终端同步机的研制

基于VXI总线系统设计了用于惯性约束聚变(ICF)实验的中等精度全程控终端同步机,可以对输出延时、幅度、极性、脉宽全面程控,并进行了性能指标测试.测试表明:该同步机固有延时小于30 ns,大信号输出脉冲前沿小于14 ns,时间抖动小于5 ns,满足了ICF实验对终端同步机的要求.     

惯性约束聚变用聚酰亚胺靶丸的研究进展

综述了近年来国内外在惯性约束聚变实验用聚酰亚胺(PI)靶丸方面的研究与应用进展情况.从ICF实验用靶的性能要求、常用PI的化学结构、PI靶丸的装配方法以及目前PI靶丸应用过程中存在的问题等几个方面进行了论述.在此基础上提出了PI靶丸的研究方向.     

惯性约束聚变靶材中间体氘代乙醛的合成与表征

氘代乙醛（ＣＤ３ＣＤＯ）是合成惯性约束聚变（ＩＣＦ）固体靶材料氘代聚苯乙烯（ＤＰＳ）的重要中间体之一。以电石（ＣａＣ２）及重水（Ｄ２Ｏ）为原料,经多步液－固,气－液化学反应,合成氘经达９９．２％,的氘代乙醛,介绍了氘代乙醛的合成工艺及其氘代率的表征方法,并对主要合成工艺参数等进行了探讨。     

惯性约束聚变靶材料碳气凝胶的制备方法

用溶胶－凝胶法制备出了高RC比（间苯二酚与催化剂的摩尔比）的RF有机气凝胶,通过溶剂替换,成功地实现了常压条件下的干燥工艺。经高温碳化处理,将RF有机气凝胶转化为碳气凝胶,改变RC比和聚合单体的质量百分数,可控制气凝胶的粒径及孔径、密度及比表面积。用扫描电镜（SEM）、BET等方法对其颗粒大小、密度、比表面积及孔径分布等微结构进行了分析测试。制备出的碳气凝胶性能满足惯性约束聚变靶材要求。     

ICF用靶丸内燃料充填参数对温度的依赖

通过BWR(Bcncdict-Wcbb-Rubin)方程研究了内径分别为100、200、400、520μm的薄壁玻璃微球在500、400、300、77、35K的温度下,其内部的压力值和在工作温度(22K)下内部液层厚度之间的对应关系。结果发现,在低温下燃料的压力比常温下低很多。     

Study of the asymmetry of hot-spot selfemission imaging of inertial confinement fusion implosion driven by high-power laser facilities

Implosion asymmetry is a crucial problem quenching ignition in the field of inertial confinement fusion. A forward-calculation method based on 1 D and 2 D hydrodynamic simulations has been developed to generate and study the x-ray images of hot-spot self-emission, indicating asymmetry integrated over the entire drive pulse. It is shown that the x-ray imaging photon energy should be higher to avoid the influence of the remaining shell. The contour level(percentage of the maximum emission intensity) and spatial resolution should be as low as possible, optimally less than 20% and 3 mm, for characterization of higher-mode signatures such as P_8–P_(12) by x-ray self-emission images. On the contrary, signatures of lower-mode such as P_2 remain clear at all contour levels and spatial resolutions. These key results can help determine the optimal diagnostics, laser, and target parameters for implosion experiments. Recent typical hot-spot asymmetry measurements and applications on the Shenguang 100 kJ class laser facility are also reported.     

Potential common radiation problems for components and diagnostics in future magnetic and inertial confinement fusion devices

This work aims at identifying common potential problems that future fusion devices will encounter for both magnetic and inertial confinement approaches in order to promote joint efforts and to avoid duplication of research. Firstly, a comparison of radiation environments found in both fusion reaction chambers will be presented. Then, wall materials, optical components, cables and electronics will be discussed, pointing to possible future areas of common research. Finally, a brief discussion of experimental techniques available to simulate the radiation effect on materials is included.     

Fatigue cracking of a bare steel first wall in an inertial confinement fusion chamber

Inertial confinement fusion power plants will deposit high energy X-rays onto the outer surfaces of the first wall many times a second for the lifetime of the plant. These X-rays create brief temperature spikes in the first few microns of the wall, which cause an associated highly compressive stress response on the surface of the material. The periodicity of this stress pulse is a concern due to the possibility of fatigue cracking of the wall. We have used finite element analyses to simulate the conditions present on the first wall in order to evaluate the driving force of crack propagation on fusion-facing surface cracks.Analysis results indicate that the X-ray induced plastic compressive stress creates a region of residual tension on the surface between pulses. This tension film will likely result in surface cracking upon repeated cycling. Additionally, the compressive pulse may induce plasticity ahead of the crack tip, leaving residual tension in its wake. However, the stress amplitude decreases dramatically for depths greater than 80–100 μm into the fusion-facing surface. Crack propagation models as well as stress-life estimates agree that even though small cracks may form on the surface of the wall, they are unlikely to propagate further than 100 μm without assistance from creep or grain erosion phenomena.     

Design and performance study of a gas-Cherenkov detector with an off-axis parabolic reflector for inertial confinement fusion experiments

In this work, the gas-Cherenkov detector with an off-axis parabolic reflector(Opr GCD) is designed using the Geant4 Monte Carlo simulation toolkit, which is helpful to improve the collection efficiency of Cherenkov photons. The method to study the performance of Opr GCD based on femtosecond laser-wakefield-accelerated electron beams is presented. Cherenkov signals with high signal-to-noise ratio were obtained, and the measured Cherenkov signals changing with the CO2 pressure were consistent well with the simulation results. The design and study of this Opr GCD system lay the foundation for the application of fusion gamma diagnostics system in large laser facilities of China.     

Multi-dimensional computational model of the movement of the solid-gas interface during the layering process in inertial confinement fusion targets in a non-uniform thermal environment

The redistribution of deuterium (DD) or of a deuterium-tritium mixture (DT) to form a layer on the inside of spherical inertial confinement fusion (ICF) capsules is a challenging problem because of the symmetry requirements of the fuel layer thickness, the smoothness requirement of the inside target surface, and the time restriction on the production process. Heat- and mass-transfer processes have been identified to interact with one another to influence the outcome of the layering process. For example, the mass redistribution speed of the fuel inside the shell towards a uniform layer and the final layer thickness uniformity depend on the variation in local heat transfer coefficient along the outer target surface.The focus of this work was to develop a numerical tool to help understand the physics involved in the layering process to be able to assess the influence of key parameters on the transient layer formation. The coupled mass and heat transfer processes governing target layering have been studied numerically, implementing unique boundary conditions to track the movement of the gas-solid boundary on the inside of the shell.The model was validated through comparison with theoretical results and laboratory-scale experiments. With this model, a window of parameters can by identified, under which layering experiments are likely to be successful.     

微焦点X辐射密度解析成像方法及非线性校正

提出了一种利用不同能量的X射线束所获得的图像来实现分离物体内部不同密度成像图像的方法。从本质上对这种算法进行了探讨,证明了这种算法的可行性;讨论了产生误差的原因,给出了对误差进行非线性校正的数学模型;并以两种成分的图像分离为例进行了实验,给出了实验结果。     

Modeling of a confinement bypass accident with CONSEN,a fast-running code for safety analyses in fusion reactors

The CONSEN (CONServation of ENergy) code is a fast running code to simulate thermal-hydraulic transients, specifically developed for fusion reactors. In order to demonstrate CONSEN capabilities, the paper deals with the accident analysis of the magnet induced confinement bypass for ITER design 1996. During a plasma pulse, a poloidal field magnet experiences an over-voltage condition or an electrical insulation fault that results in two intense electrical arcs. It is assumed that this event produces two one square meters ruptures, resulting in a pathway that connects the interior of the vacuum vessel to the cryostat air space room. The rupture results also in a break of a single cooling channel within the wall of the vacuum vessel and a breach of the magnet cooling line, causing the blow down of a steam/water mixture in the vacuum vessel and in the cryostat and the release of 4 K helium into the cryostat. In the meantime, all the magnet coils are discharged through the magnet protection system actuation. This postulated event creates the simultaneous failure of two radioactive confinement barrier and it envelopes all type of smaller LOCAs into the cryostat. Ice formation on the cryogenic walls is also involved. The accident has been simulated with the CONSEN code up to 32 h. The accident evolution and the phenomena involved are discussed in the paper and the results are compared with available results obtained using the MELCOR code.