Comparison of theoretical and experimental 3He desorption behaviour of titanium tritide films

Helium-3 formed by tritium radioactive decay from tritide layer desorbs at room temperature slowly in a first step, more strongly afterwards. A helium-3 desorption model has been established, based on the positions of He-3 atom and trapping sites in the γ tritide lattice, CaF₂ type, supposed in a perfect state. Theoretical desorption curves as a function of time or helium concentration in the layer has been computed, for metal tritide or deutero-tritide layers. Experimental curves, for a wide tritium concentration range, are given here in the case of titanium layers. They show good agreement with theoretical curves for appropriate parameter values, up to a helium/titanium atomic ratio of 0.25 to 0.30. For higher helium concentrations, rapid helium desorption can be explained by gas bubble growth and percolation, and mechanical degradation of the layer: at this stage, the theoretical model does not apply.     

LaNi5氚老化效应的实验研究

测定了老化LaNi5料的解吸等温线及去氘化热力学参数.评价了氚老化对LaNi5贮氢性能的影响.结果表明,氚老化使LaNi5解吸等温线形貌发生重大改变.与新鲜材料相比,老化2140天后,在373 K下,坪台压力降低了约50%,坪斜由0.033到0.130,可逆吸氢容量减少了约1.3 mmol.g-1.老化LaNi5料去氘化反应热力学焓变ΔH和熵变ΔS分别由30.1 kJ.mol-1和105 J.mol-1.K-1增加到44.5 kJ.mol-1和128 J.mol-1.K-1.     

Li_4SiO_4陶瓷小球水解吸行为实验研究

采用程序升温热解吸(TPD/TDS)方法对Li4SiO4陶瓷小球的水解吸行为进行了实验研究。结果表明:水解吸过程中主要存在四个解吸峰;其中100℃附近的峰可解释为物理吸附水;150,250,400℃附近的峰可分别解释为以氢键、Li-OH和Si-OH配位键形式存在的化学吸附水。氚的释放与水的解吸几乎同步进行,且氚的释放形式主要为氚水(HTO),据此推测,氚水可能存在三种释放机制:(1)-OT+H2O→-OH+HTO;(2)-OH+-OH→H2O,-OT+H2O→-OH+HTO;(3)-OT+-OH→HTO。     

Li4SiO4陶瓷小球水解吸行为实验研究

采用程序升温热解吸（TPD/TDS）方法对Li4SiO4陶瓷小球的水解吸行为进行了实验研究。结果表明：水解吸过程中主要存在四个解吸峰;其中100 ℃附近的峰可解释为物理吸附水;150,250,400 ℃附近的峰可分别解释为以氢键、Li－OH和Si－OH配位键形式存在的化学吸附水。氚的释放与水的解吸几乎同步进行,且氚的释放形式主要为氚水（HTO）,据此推测,氚水可能存在三种释放机制：（1）－OT+H2O－OH+HTO;（2）－OH+－OHH2O,－OT+H2O－OH+HTO;（3）－OT+－OHHTO。     

氦冷固态增殖实验包层安全分析研究进展综述

介绍了氦冷固态增殖实验包层(HCCB TBM)系统,该系统主要由TBM 包层、氦冷却系统、氚提取系统、冷却剂净化系统、氚计量系统和中子活化系统等组成。TBM 结构安全分析主要包括电磁安全分析、热工水力安全分析和中子学安全分析,TBM 材料安全分析主要包括结构材料安全分析、阻氚涂层和氚处理等功能材料安全分析。对国内外学者在上述安全分析研究工作中取得的研究进展进行综述,并对TBM 未来的安全分析工作进行展望,以期对其安全设计提供参考。     

LiAlO2陶瓷小球的堆外放氚行为

将LiAlO2陶瓷小球置于裂变反应堆中辐照,采用热解吸技术研究该类产氚材料的堆外放氚特性,考察了升温速率、载气组分、催化活性元素和提氚温度对氚释放行为的影响;采用电子自旋磁共振（ESR）实验技术研究了辐照缺陷的顺磁特征。结果表明:LiAlO2中氚的扩散速度慢,热解吸活化能高,氚释放主要分布在750~1000 K;表面氢同位素交换反应贡献大,释氚形态受载气条件的影响较大,当氦气中添加H2时,会增大HTO转化成HT的比例;中子辐照会在LiAlO2中诱生F+,O-和O2-等缺陷色心,其退火湮灭行为与氚释放过程存在一定关系。     

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Helium cooled ceramic breeder test blanket module (HCCB TBM) was introduced. The TBM system is mainly composed of test blanket, helium coolant system, tritium extraction system, coolant purification system, tritium measurement system and neutron activation system. The structural safety analysis of TBM mainly includes electromagnetic safety analysis, thermal-hydraulic safety analysis and neutronics safety analysis. The material safety analysis of TBM is divided into safety analysis of structural material, safety analysis of functional materials, such as tritium permeation barrier and tritium treatment materials. The research progress made by scholars at home and abroad in the above-mentioned security analysis research work was summarized, and the future safety analysis of the TBM tritium system was looked forward to, with a view to providing reference for the safety design of tritium systems.     

LiAlO_2陶瓷小球的堆外放氚行为

将LiAlO2陶瓷小球置于裂变反应堆中辐照,采用热解吸技术研究该类产氚材料的堆外放氚特性,考察了升温速率、载气组分、催化活性元素和提氚温度对氚释放行为的影响;采用电子自旋磁共振(ESR)实验技术研究了辐照缺陷的顺磁特征。结果表明:LiAlO2中氚的扩散速度慢,热解吸活化能高,氚释放主要分布在750~1000K;表面氢同位素交换反应贡献大,释氚形态受载气条件的影响较大,当氦气中添加H2时,会增大HTO转化成HT的比例;中子辐照会在LiAlO2中诱生F+,O-和O2-等缺陷色心,其退火湮灭行为与氚释放过程存在一定关系。     

Tritium planigraphy as a tool for studying the structural organization nanobiocomplexes

The tritium planigraphy method is based on the nonselective substitution of radioactive isotope tritium for hydrogen in hydrocarbon fragments of molecules by means of a chemical reaction involving hot tritium atoms. Data on the steric accessibility of the system components (macromolecules in the complex, amino acid residues, and even individual atomic groups of macromolecules) characterize the structure of the object. The method, applicable to substances in different phase states, has no restrictions on the molecular weight of the target. Tritium planigraphy, used equally successfully in both crystals and solutions, makes it possible to study fine changes in the structure. The main results of studies of the structure of nanosized biocompexes by tritium planigraphy are presented.     

氚钛薄膜靶中氚深度分布的反演

金属氚化物中体相氚的总量和深度分布测定是体相中氚行为研究的难点,利用氚衰变诱发X射线谱的氚分析技术分析了金属薄膜靶中体相氚的深度分布情况,建立了薄膜靶中氚深度分布计算模型,利用Tikhonov正则化方法反演了薄膜靶中体相氚的深度分布。反演结果表明,正则化数值算法能够有效提高对薄膜靶法向非均匀性的分辨。     

AC losses dependence on a CuNi layer location in NbTi CICC

In the frame of the ITER fusion program, large Cable In Conduit Cables (CICC) made with NbTi superconductors are foreseen for the poloidal field system. These coils are pulsed and so subjected to fast variations in magnetic field. Superconductors have then to be designed in order to reduce AC losses to an acceptable level. A solution could be to insert a copper nickel resistive barrier in the copper stabilizer surrounding the filamentary area of the composite. The purpose of this barrier is to reduce interstrand coupling currents. In order to predict the effect of this barrier on AC losses, a modeling of a 36 strands CICC has been realized. According to this code, the ability of the resistive barrier to reduce coupling currents is dependent on its location. For this study, three CICC with three barrier locations, from the inner to the outer diameter of the copper crown stabilizer, have been produced. AC losses have been measured and compared to our numerical model.     

高压氘氚靶球的制备与拉曼光谱研究

氢同位素的定量分析与监测在能源与环境领域都有着重要的意义。激光拉曼光谱由于其可以无损分析氢同位素分子,已经成为一种重要的方法,在国际热核聚变实验反应堆(ITER)和美国萨凡纳河工厂得到了广泛应用。利用高压充气装置得到了惯性约束聚变(ICF)高压靶丸,并对靶丸内气体进行原位拉曼光谱测量,通过对高压下氘氚混合气体的拉曼光谱进行分析得到了靶丸内气体的成分比例,验证了靶丸充气工艺参数。实验表明,在CCD的积分时间延长到1 min时,氘(DD),氘氚(DT)和氚(TT)的测量精度可以达到1%,同时对不同时刻靶丸内气体组分的拉曼光谱进行测量,实验结果表明在氘氚渗透和氚衰变两者共同作用下,靶丸内总气体压力随时间不断下降,但是气体组成基本不发生变化。     

Modification of surface oxide layers of titanium targets for increasing lifetime of neutron tubes

The peculiarities of interaction of hydrogen ions with a titanium target and its surface oxide layer were studied. Two ways of modification of the surface oxide layers of titanium targets for increasing the lifetime of neutron tubes were proposed: (1) deposition of an yttrium oxide barrier layer on the target surface; (2) implementation of neutron tube work regime in which the target is irradiated with ions with energies lower than 1000 eV between high-energy ion irradiation pulses.     

Cryogenic hydrogen fuel for controlled inertial confinement fusion (formation of reactor-scale cryogenic targets)

In inertial fusion energy research, considerable attention has recently been focused on low-cost fabrication of a large number of targets by developing a specialized layering module of repeatable operation. The targets must be free-standing, or unmounted. Therefore, the development of a target factory for inertial confinement fusion (ICF) is based on methods that can ensure a cost-effective target production with high repeatability. Minimization of the amount of tritium (i.e., minimization of time and space at all production stages) is a necessary condition as well. Additionally, the cryogenic hydrogen fuel inside the targets must have a structure (ultrafine layers—the grain size should be scaled back to the nanometer range) that supports the fuel layer survivability under target injection and transport through the reactor chamber. To meet the above requirements, significant progress has been made at the Lebedev Physical Institute (LPI) in the technology developed on the basis of rapid fuel layering inside moving free-standing targets (FST), also referred to as the FST layering method. Owing to the research carried out at LPI, unique experience has been gained in the development of the FST-layering module for target fabrication with an ultrafine fuel layer, including a reactor- scale target design. This experience can be used for the development of the next-generation FST-layering module for construction of a prototype of a target factory for power laser facilities and inertial fusion power plants.     

Pd-Ag膜电解浓缩氚的动力学模型及理论计算

建立了模拟Pd-Ag合金膜电解浓缩氚的过程和诸多电解参数的动力学模型。采用求解数学扩散方程的方法得到理论值,并与文献报道的实验数据进行比较。计算结果表明：氚在Pd-Ag膜上的吸附、解吸、浓缩等行为受到诸多条件的制约。在保证密封性能的前提下,对Pd-Ag膜电解槽体的要求是至少应包括有含氚水路循环、阳极气体消除和阴极扩散后氚再生3个组成部分,采取相匹配的级联技术可以提高分离效果;对电解参数的要求是采取尽可能高的电解液温度和稳定的OH^-浓度,合适的电流密度,合理的膜厚度、表面特征和Pd黑结合紧密。     

Mechanism of H2 desorption from monohydride Si(100)2 × 1H

Most recent experimental work on H₂ desorption from the monohydride Si(100) surface seems to point to a pairwise desorption mechanism involving the concerted desorption of two hydrogen atoms on different Si atoms of a single dimer. Using ab initio SCF and CI theory and a cluster model of the surface, the present work finds that the lowest energy pathway is symmetric rather than asymmetric. The desorption energy barrier is calculated to be 3.7 eV. Compared with an experimental value of 2.6 eV, the large barrier suggests that this direct desorption mechanism is not applicable. A multi-step desorption mechanism which involves a delocalized process in the formation of dihydride SiH₂ and a localized desorption of H₂ is proposed and is shown to explain the experimental observations.     

Kinetics of desorption from adsorbed layers formed by two-dimensional islands and by a two-dimensional gas

The kinetics of desorption from the adsorbed layers formed by two-dimensional (2D) islands and by a 2D gas of single atoms is considered for the case when the flux of adsorbate atoms from the gaseous phase reaches the surface. The effect of this flux on the desorption kinetics is analyzed. It is shown that this effect can be disregarded when the islands are in equilibrium with the surrounding 2D gas. The possibilities of determining the energy required for the removal of atoms from 2D islands to a vacuum are considered for the case of the absence of equilibrium in adsorbed layers. The conditions under which such a determination is possible are formulated, and the corresponding recommendations for experimental studies are worked out.     

Reduced filament coupling in Bi(2223)/BaZrO3/Ag composite tapes

Multifilamentary Bi(2223)/Ag tapes often exhibit AC loss levels comparable to those measured in monofilamentary samples, which is partly due to the large coupling currents induced in the low resistive sheath material. Surrounding the individual filaments by electrically insulating barrier layers suppresses these currents and strongly reduces the coupling. We demonstrate this effect with various types of magnetic and self-field AC loss measurements on a series of Bi(2223)/BaZrO₃/Ag tapes. We also discuss the influence of barrier thickness, twist pitch length and filament arrangement on the measured losses in these composite conductors.     

Tritium recovery from co-deposited layers using 193-nm laser

Recovery of tritium from co-deposited layers formed in deuterium–tritium plasma operations of the TFTR (Tokamak Fusion Test Reactor) was investigated by the use of an ArF excimer laser operating at the wavelength of 193 nm. At the laser energy density of 0.1 J/cm², a transient spike of the tritium-release rate was observed at initial irradiation. Hydrogen isotopes were released in the form of hydrogen-isotope molecules during the laser irradiation in vacuum, suggesting that tritium can be recovered readily from the released gases. In a second experiment, hydrogen (tritium) recovery from the co-deposited layers on JT-60 tiles that had experienced hydrogen-plasma operations was investigated by laser ablation with a focused beam of the excimer laser. The removal rate of the co-deposited layers was quite low when the laser energy density was smaller than the ablation threshold (1.0 J/cm²), but reached 1.1 μm/pulse at the laser energy density of 7.6 J/cm². The effective absorption coefficient in the co-deposited layers at the laser wavelength was determined to be 1.9 μm^-1. The temperature of the surface during the irradiation at the laser energy density of 0.5 J/cm² was measured on the basis of Planck’s law of radiation, and the maximum temperature during the irradiation decreased from 3570 K at the initial irradiation to 2550 K at the 1000th pulse of the irradiation. Received: 5 August 2002 / Accepted: 7 August 2002 / Published online: 28 October 2002 RID="*" ID="*"Corresponding author. Fax: +81-29/2825917, E-mail: shu@tpl.tokai.jaeri.go.jp     

Fast ignition by detonation in a hydrodynamic flow

A general concept of fast ignition by a hydrodynamic pulse is developed. The main statements of the concept are formulated having in mind the need to ignite the pre-compressed thermonuclear fuel of the inertial confinement fusion (ICF) target. Initially, combustion must be initiated inside the hydrodynamic flow during its action on the target. The conditions for propagating a self-sustaining thermonuclear-detonation wave from an igniter on the thermonuclear fuel of the ICF-target must be provided. For this, the deuterium–tritium (DT) igniter placed in the forward part of the hydrodynamic flow should not only be heated up to thermonuclear temperature, but also compressed to a density close to the density of the ICF-target fuel. It is shown that the detonation of the multilayer conical target (containing DT-ice and a heavy pusher) enables fast ignition of the ICF target fuel of 200–500 g/cm³ density at an implosion velocity of 300–500 km/s.