Applications of Skyrme Energy-Density Functional to Fusion Reactions Spanning Fusion Barriers

在加速器驱动次临界系统（ADS）项目中，由我院承担研制的强流RFQ注入系统，包括ECR强流离子源及束流低能传输线（LEBT），从2005年8月移机中国科学院高能物理研究所后，历时半年多时间，解决了由于工作环境改变而带来的一系列水、电、气问题，包括电器系统供电与控制的改造，     

Applications of Skyrme Energy-Density Functional to Fusion Reactions for Synthesis of Superheavy Nuclei

The Skyrme energy-density functional approach has been extended to study the massive heavy ion fusion reactions. Based on the fusion barrier obtained and the parameterized barrier distribution the fusion （capture） excitation functions of a lot of heavy-ion fusion reactions are studied systematically.     

Applications of Skyrme Energy-Density Functional to Fusion Reactions for Synthesis of Superheavy Nuclei

It is of great importance to predict fusion cross sections and to analyze reaction mechanism for massive heavy-ion fusion reactions, especially for fusion reactions leading to superheavy nuclei. In those reactions, the calculation of the capture cross section is of crucial importance. It is known that Wong＇s formula based on one-dimensional barrier penetration can describe the fusion excitation function well for light reaction systems, while it fails to give satisfying results for heavy reaction systems at energies near and below the barrier. For solving this problem, we applied the Skyrme energy-density functional for the first time to study heavy-ion fusion reactions. The barrier for fusion reaction was calculated by the Skyrme energy-density functional together with the semi-classical extended Thomas-Fermi method.     

Reducing the Barriers to Fusion Electric Power

A potential solution to some of the current problems faced by the U.S. Magnetic Fusion community is presented. It can be implemented with little or no increase in the present funding level and it could promote a more positive attitude toward what is, in its ultimate application to electricity generation, a very long and costly research program. The proposed solution is to devote a significant fraction of the current program to developing, and marketing, near term commercial products from low Q devices. It is anticipated that such a research and development program is in fact less expensive than the pursuit of very large and complex toroidal power plants based on the DT cycle. A few examples of near term commercial products are discussed and a plan presented that could ultimately lead to economical and environmentally attractive fusion power plants.     

Nonelectric Applications of Fusion

This is the final report of a panel set up by the U.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee (FESAC) in response to a charge letter from Dr. James Decker, Acting Director of the DOE Office of Science. In that letter, Dr. Decker asked FESAC to consider whether the Fusion Energy Sciences program should broaden its scope and activities to include non-electric applications of intermediate-term fusion devices. This report, submitted to FESAC July 31, 2003, and subsequently approved by them (Appendix B), presents FESAC's response to that charge.     

Energy Dependence of Dynamic Barrier in Heavy-Ion Fusion Reactions

投影壳模型（PSM）给出的波函数具有好的角动量和宇称，并且不断证实它可以很好地描述原子核的多方面性质。本工作期望采用PSM波函数计算Beta衰变矩阵元能够给出较好的结果。最近，应用投影壳模型初步建立了Gamov—Teller（GT）跃迁的计算程序。     

Thermal Shock Behavior of SiC Coatings for Fusion Reactor Applications

Graphite substrate ISEM-3 whose thermal expansion coefficient is close to that of SiC and graphite substrate AXF-5Q1 whose thermal expansion coefficient is larger than that of SiC were coated with 50–200 μm thick CVD-SiC. On the AXF-5Q1 graphite substrate SiC could not be completely coated. Additionally HSC-SiC, which has SiC conversion layer of 800 μm thickness and whose thermal expansion coefficient of the graphite substrate is close to that of SiC, was also tested. Thermal shock test was carried out by electron beam of accelerating voltage of 10 kV, beam current of 50–200 mA, beam diameter of about 10 mmø and heating time of a single pulse of 30 s. Crack was not observed on the CVD-SiC coating on the ISEM-3 graphite even at 200 mA (about 2.5kW/cm²) and hole of about 1 mm in diameter was observed and the graphite substrate was revealed. Additionally for thermal cycle test (1,000 times, ΔT=950°C), the crack or spalling was not observed on the CVD-SiC coating. It was found that for the HSC-SiC the hole was only observed with the single pulse of 200 mA and the crack was not observed. Thus the HSC-SiC also may be a candidate as the first wall of the fusion reactors.     

Neutron Response Calculations of Alpha-Track Detector for Fusion Neutronics Applications

The neutron energy dependent response of the α-track detector, cellulose nitrate film (Kodak LR-115 type I) in contact with a lithium radiator was calculated. The “mean effective thickness L _eff” of the radiator is obtained as a function of the neutron energy and incident angle. The distribution of the etched-through-track density is evaluated from the calculated L _eff and compared with the measured results in the fusion blanket assembly.     

我国聚变堆结构材料表面阻氚涂层的研究进展

阻氚涂层是聚变堆实现氚自持及氚安全的关键科学与技术问题之一。我国通过国家磁约束聚变能发展研究专项依托国内优势单位部署了阻氚涂层基础问题及工程化技术研发工作。本文介绍了国内外聚变堆结构材料表面阻氚涂层研究进展,重点评述了近几年我国在阻氚涂层的材料选择、制备技术及阻滞氢渗透机制三个科学技术问题的研究进展,提出今后的研究方向。目前我国阻氚涂层材料类型以氧化物涂层为主,涂层制备工艺技术在不断优化和更新。Al2O3/FeAl阻氚涂层的电化学沉积铝(ECA)、粉末包埋渗铝(PC)及热浸铝(HDA)等方法的工艺处理规模及涂层阻氚性能在国际上均相对领先。发展了研究阻氚涂层阻滞氢渗透作用机理的方法,将通常基于Fick定律的表象研究方法向原子级方法前推了一步。未来需在考虑涂层制备工艺与基体材料成分、性能的关系及其在复杂形状结构件的适用性基础上,开发长寿命、高阻氚性能的阻氚涂层材料及制备工艺。     

Calculations of Proton Emission Cross Sections in Deuteron Induced Reactions of Some Fusion Structural Materials

The growing demands for energy consumption have led to the increase of the research and development activities on new energy sources. Fusion energy has the highest potential to become a very safe, clean and abundant energy source for the future. To get energy from fusion are needed for development of fusion reactor technology. Particularly, the design and development of international facilities as International Thermonuclear Experimental Reactor and International Fusion Material Irradiation Facility requires for the cross-section data of deuteron induced reactions. Moreover, the selection of fusion structural materials are an indispensable component for this technology. Therefore, the cross-section data of deuteron induced reactions on fusion structural materials are of great importance for development of fusion reactor technology. In this study, reaction model calculations of the cross sections of deuteron induced reactions on structural fusion materials such as ²⁷Al, ⁵⁹Co, ⁵⁵Mn, ⁵⁰Cr, ⁵⁴Cr, ⁶⁴Ni, ¹⁰⁹Ag, ¹⁸⁴W and ¹⁸⁶W have been carried out for incident energies up to 50 MeV. In these calculations, the pre-equilibrium and equilibrium effects for (d,p) stripping reactions have been investigated. The pre-equilibrium calculations involve the new evaluated the geometry dependent hybrid model and hybrid model. Equilibrium effects are calculated according to the Weisskopf-Ewing model. In the calculations the program code ALICE/ASH was used. The calculated results are discussed and compared with the experimental data taken from the literature.     

Dynamic Study on Entrance-Channel Effects of Symmetry and Asymmetry Reaction System in Heavy-Ion Fusion Reactions

The entrance-channel effects and dynamical mechanisms on the fusion reaction of the symmetry and asymmetry reaction system are studied with the microscopic transport model, i.e. Improved Quantum Molecular Dynamic Model （ImQMD）. From the microscopic dynamical point of view, the relation of the intensity in the population of the superdeformed bands of high-spin states and the entrance-channel effects is explored in the heavy-ion fusion reactions. Two different fusion-evaporation reactions are selected：     

Investigation of Some Stellar Iron Group Fusion Materials for (n, p) Reactions

In this study, we present the results of a careful analysis of cross sections of some important iron (Fe) group target elements (20 ≤ Z≤28) for astrophysical (n, p) reactions such as Si, Ca, Sc, Ti, V, Cr, Fe, Co and Ni used in neutron activation analysis have been investigated. The new calculations on the excitation functions of ²⁸ Si(n, p) ²⁸ Al, ²⁹ Si(n, p) ²⁹ Al, ⁴² Ca(n, p) ⁴² K, ⁴⁵ Sc(n, p) ⁴⁵ Ca, ⁴⁶ Ti(n, p) ⁴⁶ Sc, ⁵¹ V(n, p) ⁵¹ Ti, ⁵² Cr(n, p) ⁵² V, ⁵³ Cr(n, p) ⁵³ V, ⁵⁴ Fe(n, p) ⁵⁴ Mn, ⁵⁷ Fe(n, p) ⁵⁷ Mn, ⁵⁹ Co(n, p) ⁵⁹ Fe, ⁵⁸ Ni(n, p) ⁵⁸ Co and ⁶⁰ Ni(n, p) ⁶⁰ Co reactions have been carried out up to 25 MeV incident neutron energy. In these calculations, the pre-equilibrium and equilibrium effects have been investigated. Equilibrium effects are calculated according to the Weisskopf–Ewing model. The pre-equilibrium calculations involve the geometry dependent hybrid model, hybrid model and equilibrium model. Also in the present work, these reaction cross-sections have been calculated by using evaluated empirical formulas developed by Tel et al. at 14.7 MeV energy. The calculations are compared with existing experimental data as well as with evaluated data files (Experimental Nuclear Reaction Data (EXFOR). According to these calculations, we assume that these model calculations can be applied to some heavy elements, ejected into interstellar medium by dramatic supernova events.     

Near Term Applications of Plasma Science and Fusion Research: National Laboratory Perspectives

This paper describes some of the near-term practical applications of plasma science from the perspective of National Laboratories involved with fusion research for many years. The first half of the paper presents suggestions for maintaining a healthy national program in this area. The second part of the paper gives specific examples of near-term plasma applications research at our laboratories.     

聚变堆用难变形CLAM钢三通成形模拟及试验研究

利用有限元软件对聚变堆用CLAM钢三通管件的内高压整体成形工艺进行了数值模拟,研究了压力加载路径及摩擦条件关键工艺参数对支管高度以及壁厚分布的影响,从而确定了CLAM钢三通管件内高压成形的优化工艺参数组合。使用满足优化摩擦系数的表面涂层对CLAM钢管坯进行润滑处理,并根据优化结果对CLAM钢管材进行了内高压成形试验。实际成形的三通管件在几何尺寸及厚度分布方面,实验结果和模拟结果吻合。研究结果表明,通过有限元数值模拟可准确预测难变形材料CLAM钢三通的复杂冷成形,并确定工艺参数;通过确定的工艺参数可制备出几何尺寸及厚度分布均满足要求的高质量聚变堆用三通管件。     

The Role of Magnetized Liner Inertial Fusion as a Pathway to Fusion Energy

We discuss the possible impacts of a new magnetized liner inertial fusion concept on magneto-inertial fusion approaches to fusion energy. Experiments in the last 1.5 years have already shown direct evidence of magnetic flux compression, a highly magnetized fusing fuel, significant compressional heating, a compressed cylindrical fusing plasma, and significant fusion yield. While these exciting results demonstrate several key principles behind magneto-inertial fusion, more work in the coming years will be needed to demonstrate that such targets can scale to ignition and high yield. We argue that justifying significant investment in pulsed inertial fusion energy beyond target development should require well-understood, significant fusion yields to be demonstrated in single-shot experiments. We also caution that even once target ideas and fusion power plants have been demonstrated, historical trends suggest it would still be decades before fusion could materially impact worldwide energy production.     

Studying the Effects of Compound Nucleus Energy on Coefficient of Surface Tension in Fusion Reactions Using Proximity Potential Formalism

In this investigation, the energy effects of compound nucleus are studied using formalism of proximity potential on the surface tension coefficient (γ). For this purpose, this coefficient in both main and final versions of proximity formalism, which are: Prox.77 and Prox.2010, is corrected based on systematic studying on 60 of fusion reactions. The correction in γ is caused to improve agreeing fusion cross sections with empirical amounts of them specifically in sub-barrier energies. This correction has significant effect on increasing the theoretical amounts of cross sections in the range of Coulomb sub-barrier energies. The produced results show improvement of agreement on theoretical amounts of Coulomb barrier height with corresponding laboratory data in the various collision systems. In addition, the obtained results show that the MP.2010 potential is able to produce laboratory data more accurate rather than other introduced potentials.     

Examples of Industrial Contributions to Fusion Development

A number of examples are given of contributions to by U.S. industry to fusion energy development.