氚靶生产现场氚监测系统的构建

氚靶生产过程中的氚监测是保障工作安全进行的有力条件。通过建立1套中央控制多区域监测子系统,并辅之以便携式监测仪器及取样设备,构建成1套完整的氚靶生产现场氚监测系统。系统在氚靶生产过程中得以应用,结果表明,中央控制多区域监测系统的响应时间小于10s,其它设备运行正常,能很好地满足氚靶生产现场的监测要求。     

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。     

Development of Merged Compact Toroids for Use as a Magnetized Target Fusion Plasma

We report on the development of compact toroid (CT) accelerators to create the target plasma for magnetized target fusion (MTF) devices. Due to the requirements of high initial density of ~10¹⁷ cm⁻³, strong internal fields of 5–10 T, and base temperatures of >100 eV, a design based on conical compression electrodes is an effective avenue to pursue. Progress is being made at General Fusion Inc, (Vancouver, Canada) to develop a pair of large CT accelerators for generating an MTF target plasma. In this design, tungsten coated conical electrodes (with a formation diameter of 1.9 m, a radial compression factor of 4, and overall accelerator length of 5 m) will be used to achieve ohmic heating and acceleration of the CT, yet with low wall sputtering rates. A pair of these accelerators can be synchronized and shot at one another, producing a collision and reconnection of the two CTs within the center of an MTF chamber. Depending on the choice of relative helicities, the two CTs will merge to form either a spheromak-like or an FRC-like plasma. ICC 2008 Reno NV, June 25th, IP: 021.     

Development of In-Situ Gas Analyzer for Hydrogen Isotopes in Fusion Fuel Gas Processing

To develop a real time and in-situ process gas analyzer for fusion fuel gas processing systems, application study of laser Raman spectroscopy was performed by measurement of hydrogen isotopes. Using an Ari on type laser of which wavelength 488 nm, power 0.7 W, and single pass irradiation method, Raman spectra of hydrogen isotopes were measured and intensities of the Stokes rotational lines and Q-branch were quantitatively analyzed. The Stokes rotational lines at 587, 443 and 415 cm¹ were selected as suitable ones for quantitative analysis of H₂, HD and D₂. Normalizing the Raman intensity of partial pressure H₂ as 100, relative Raman intensity ratio of H₂:HD:D₂ was obtained as 100:58:47. The detection limit for hydrogen was estimated as 0.05 kPa in partial pressure and 500 ppm in concentration. But multiple pass method further improved the detection limit to 100 ppm.     

ICF分解实验中的平面调制靶和薄膜靶的研制

本工作研制了用于惯性约束聚变ICF分解实验模拟聚变靶丸表面粗糙度和驱动激光空间不均匀性对R—T不稳定性作用的平面调制靶和平面薄膜靶。以激光干涉法结合图形转移工艺获得波长20～100μm、振幅0．0～4．0μm的正弦调制图形的模板,再将调制图形转移至溴代聚苯乙烯薄膜表面,制备出ICF实验用溴代聚苯乙烯平面调制箔靶;以半导体工艺结合自截止腐蚀工艺制得厚度4μm左右的自支撑Si平面薄膜靶。Si膜的表面粗糙度为几十纳米。对所研制的两种靶型的参数进行了测量。     

8-羟基喹啉铝/酞菁/聚苯乙烯平面靶的激光烧蚀特性

新型高效靶丸结构设计中,内爆靶表面引入某些有机双层薄膜结构可使部分能量沿薄膜的平面传输,使其对称压缩靶丸,实现高效的内爆。文章在PS平面靶表面蒸镀双层功能薄膜,薄膜为8-羟基喹啉铝(Alq₃)/酞菁(H₂Pc)或苯并咪唑苝(PV)/H₂Pc。并对其进行了荧光光谱分析和激光烧蚀实验。研究表明：双层薄膜Alq₃/H₂Pc和PV/H₂Pc产生很强的荧光淬灭;由于该结构横向传输载流子的光电特性,Alq₃/H₂Pc和PV/H₂Pc在很大程度上减弱了PS薄膜的烧蚀,且烧蚀面积分别为无涂层PS薄膜烧蚀面积的8倍和3倍。为新型高效惯性约束聚变靶的设计开发提供了一种新颖的靶丸结构。     

Neutronics Calculations in Pellets and Blankets of Laser Fusion Reactor Concept SENRI-I

The neutronic properties of SENRI-I, a reference design of laser fusion reactor proposed by Institute of Engineering, Osaka University, are discussed on the basis of the one-dimensional neutron transport calculations in burning DT plasmas and blankets. The softening of the fusion neutron energy spectrum, the neutron heating and the neutron multiplication are studied and discussed for the compressed DT pellets with various thickness of fuel plasmas and lead or lead-polyethylene tampers.

The neutronic and thermal features in the blanket of the SENRI-I design are also examined. The tritium breeding ratio is high enough (~1.6), depending on the neutron energy spectrum from a pellet. The maximum temperature increase per 1,000 MJ DT fusion reactions is ~3°C in the inner liquid Li layer and ~1.5°C in the stainless steel first wall. A parametric study is also presented on the effect of varying the thickness of the inner Li blanket ΔRⁱ to examine the thickness required for the enough tritium breeding ratio and energy deposition.     

Progress of Laser Fusion Research with GEKKO XII Glass Laser and KONGHO Project for Breakeven

The progress of laser fusion research is remarkable in obtaining the high density (100 times solid density) and high temperature plasma and in the understanding of the implosion physics. Thermonuclear neutrons of 1013 per shot and pellet gain of 0.2% have been achieved. The data bases of the laser fusion have been accumulated for the fusion ignition experiment and the achievement of the breakeven condition is estimated to be possible with 100 kJ blue laser.     

整体式空腔Cu靶的化学镀制备工艺

对整体式空腔 Cu 靶的化学镀制备工艺和靶表面抗腐蚀处理进行了研究。选用有机玻璃(PMMA)作芯铀,对芯轴表面活化处理,在芯轴表面化学镀 Cu,再用苯骈三氮唑(C6H5N3)溶液钝化处理Cu靶表面,溶蚀芯轴,最终获得整体式空腔 Cu靶。该法工艺简单,制备费用较低,对惯性约束聚变研究所需其它金属或合金空腔靶的制备具有较高的参考价值。     

Effects of Sputtering of and Radiation by Aluminum on Magnetized Target Fusion Plasmas

We estimate numerically the rate of radiation by aluminum impurities for parameters relevant to magnetized target fusion (MTF) plasmas. We demonstrate that the coronal equilibrium is appropriate for expected MTF plasma parameters. Using the coronal equilibrium, we estimate the power radiated per impurity ion is 0.25–0.5 × 10⁻¹⁶ MW for temperatures and densities relevant to present plasma parameters taken from the FRX-L experiment at Los Alamos National Laboratory and is approximately 75.0 × 10⁻¹⁶ MW for temperatures and densities relevant to anticipated MTF plasmas. We calculate the sputtering rate of aluminum by thermal deuterium and tritium plasma ions is a few percent assuming an impact angle of 45°. Finally, we estimate that with aluminum impurity levels of a few percent, the impurity radiation power density would be approximately 25 kW/cm³ for FRX-L conditions and 2.5 GW/cm³ for anticipated conditions in a MTF plasma. While we have assumed a sputtering model of impurity generation, the results for the power density apply for impurity levels of a few percent, regardless of the generation mechanism.     

Development of Neutronics Studies for Fusion

Typical integral experiments using the 14 MeV neutrons concerning fusion neutronics are reviewed briefly, which have been performed in the last 20 years in lapan. Emphasis has been put upon some integral experiments on the tritium production rates in lithium-oxide systems by 1AERI group and a lithium metal sphere by university group. Integral tests of nuclear data files for several kinds of structural materials have been also carried out. It is expected that these results will be useful to enhance accuracy or the nuclear data evaluations and reactor blanket design.     

激光直接驱动内爆中子产额实验诊断

利用激光驱动充 DT燃料的内爆靶丸 ,完成了“神光 ”激光装置首轮内爆出中子实验。通过超快猝灭塑料闪烁探测器测到了直接驱动内爆中子产额。中子产额 10 7～ 10 9,测量误差± 7%～± 10 %。中子产额实验值与理论部提供的计算值 (爆推靶 )在± 2 0 %范围内一致。     

Overview of Safety and Environmental Issues for Inertial Fusion Energy

This paper summarizes safety and environmental issues of Inertial Fusion Energy (IFE): inventories, effluents, maintenance, accident safety, waste management, and recycling. The fusion confinement approach among inertial and magnetic options affects how the fusion reaction is maintained and which materials surround the reaction chamber. The target fill technology has a major impact on the target factory tritium inventory. IFE fusion reaction chambers usually employ some means to protect the first structural wall from fusion pulses. This protective fluid or granular bed also moderates and absorbs most neutrons before they reach the first structural wall. Although the protective fluid activates, most candidate fluids have low activation hazard. Hands-on maintenance seems practical for the driver, target factory, and secondary coolant systems; remote maintenance is likely required for the reaction chamber, primary coolant, and vacuum exhaust cleanup systems. The driver and fuel target facility are well separated from the main reaction chamber.     

Present Status and Future Prospects of Laser Fusion Research at ILE Osaka University

Reviewed are the present status and future prospects of the laser fusion research at the ILE Osaka.The Gekko XII and Peta Watt laser system have been operated for investigating the implosion hydrodynamics,fast ignition, and the relativistic laser plasma interactions and so on.In particular,the fast ignition experiments with cone shell target have been in progress as the UK and US-Japan collaboration programs.In the experiments,the imploded high density plasmas are heated by irradiating 500 J level peta-watt laser pulse.The thermal neutron yield is found to increase by three orders of magnitude by injecting the peta-watt laser into the cone shell target.The Rayleigh-Taylor instability experiment results are also reviewed is this paper.     

Preliminary Study of Isotopic Methanes Analysis by Laser Raman Spectroscopy for In-Situ Measurement at Fusion Fuel Gas Processing

Application of laser Raman spectroscopy for fusion fuel gas processing was studied by measuring isotopic methanes exchanged with hydrogen isotopes, which are considered to be a major impurities in the processing. For experimental gases, isotopically equilibrated deuterium and methane were prepared in the presence of solid catalyst. Large Raman scattering peaks of v ₁, bands were observed at 2,917 cm^?1 for CH₄ and at 2,100-2,200 cm_?1 for deuterated derivatives of methane C(H,D)₄. Under a spectral resolution of 5 cm_?1, the v ¹ bands of CH₃D and CH₂D₂ were observed as an overlapped peak, the relative absolute Raman intensity ratio of each isotopic methane was obtained as CH₄: CH₃D+CH₂D₂: CHD₃: CD₄=230: 74: 144: 100. On the other hand, the Raman intensity ratio obtained from pure deuterated standard methane was CH₄: CH₃D: CH₂D₂: CHD₃: CD₄=230: 53: 33: 115: 105. It was confirmed that isotopically equilibrated hydrogen isotopes and methane mixed gas would be applicable for an alternative standard gas for fusion fuel processing gas analyzing system.     

Thick Lithium Metal Target for Fast Neutron Production

A high flux fast neutron was produced by the (d, n) reaction of a lithium metal target. A thick lithium layer for the target was prepared by a simple method of melt-coating on a copper plate. The fast neutron (>9 MeV) flux at a distance of 6mm from the target was (9.0±1.6)×l0⁶ n/cm²·sec·μA with use of a 2.0 MeV deuteron beam. A flux of 2.7×10⁹ n/cm²·sec was obtained by bombarding the target with the deuteron beam of 300 μA.     

聚苯乙烯/Al双介质调制靶的研制

介绍了用于流体力学不稳定性实验的聚苯乙烯（CH）/Al双介质调制靶的制备方法。采用激光微加工工艺在50 μm厚Al箔表面制备了调制周期为55 μm、峰谷差为4.7 μm的调制图形;采用旋涂工艺在Al箔表面制备了20 μm厚CH薄膜,经过后期的微切割、微装配工艺,得到了宽度为200 μm、总厚度为70 μm的CH/Al双介质调制靶。该靶型于2010年在“神光-Ⅱ”激光装置中进行了流体力学不稳定性实验。     

Solving the Stand-off Problem for Magnetized Target Fusion: Plasma Streams as Disposable Electrodes, Together with a Local Spherical Blanket

In a fusion reactor based on the magnetized target fusion approach, the permanent power supply has to deliver currents up to a few mega-amperes to the target dropped into the reaction chamber. All the structures situated around the target will be destroyed after every pulse and have to be replaced at a frequency of 1–10 Hz. In this paper, an approach based on the use of spherical blanket surrounding the target, and pulsed plasma electrodes connecting the target to the power supply, is discussed. A brief analysis of the processes associated with creation of plasma electrodes is presented.     

激光靶丸全表面检测与功率谱特征评价

本工作基于靶丸全球面测量的经纬迹线法,应用由原子力显微镜、精密回转气浮轴系及辅助转位轴系等组成的靶丸表面形貌测量系统,对直径0.34mm的空心塑料靶丸表面进行了测量实验。实验选择了圆周9条经圆(间隔20°),每个经圆方向上纬圆间隔10μm,最大偏移20μm的方案,获取了靶丸全球面的经纬测量迹线,并对测量结果进行了模数-功率谱特征曲线和表面均方根粗糙度的分析。     

10~(12)n/s氘氚聚变中子发生器旋转氚靶设计与传热分析

本文设计一种用于1012 n/s量级氘氚中子发生器HINEG(High Intensity Neutron Generator)的旋转氚靶系统,对该系统的技术难点、机械和冷却方案等进行介绍,给出了该靶系统的设计关键指标参数,并利用CFD方法对该旋转靶系统的传热过程进行三维模拟和分析。分析结果表明,该靶系统在稳定运行时,靶片最高温度为48℃,靶系统采用的冷却方案可以有效地实现靶系统的散热,不会发生氚的大量释放和靶片熔毁。