国际热核聚变堆实验增殖包层模块设计

为了验证国际热核聚变堆（ITER）的产氚和能量获取等性能,各国分别提出了不同的实验增殖模块（TBM）设计方案。其总体功能相同,但具体技术路线有区别,不同之处包括冷却剂选择、产氚材料选择、中子倍增剂选择、产氚区布置形式、面向等离子体材料选择、结构材料选择等方面。通过对各TBM方案进行比较分析,评价了各自的优缺点,提出了未来先进产氚包层方案的设计建议。     

国际热核聚变堆实验增殖包层模块设计

为了验证国际热核聚变堆(ITER)的产氚和能量获取等性能,各国分别提出了不同的实验增殖模块(TBM)设计方案。其总体功能相同,但具体技术路线有区别,不同之处包括冷却剂选择、产氚材料选择、中子倍增剂选择、产氚区布置形式、面向等离子体材料选择、结构材料选择等方面。通过对各TBM方案进行比较分析,评价了各自的优缺点,提出了未来先进产氚包层方案的设计建议。     

热核聚变实验堆中超导母线绝缘层的红外热波检测

本项研究的目的在于探索热核聚变实验堆中超导母线绝缘层的主动式 红外热波检测方法.文中用装有热水的薄膜袋对预埋脱黏缺陷的试件表面进行接触热激励; 给出了在面热源作用下长圆柱内一维瞬态导热的近似理论模型;通 过对理论模型的模拟和分析,发现对热波降温信号进行微分处理可有效提高缺陷和 非缺陷信号对比度;与闪光灯激励的结果进行比较,显示接触热激励的检测深度优于 闪光灯脉冲热激励.     

Adhesion-diffusion formation of a multilayer wall for the liquid metal flow channel of a fusion reactor blanket

A technique for calculating the adhesion-diffusion formation of a multilayer metal-ceramic structure is presented. The development of this technique is dictated by requirements imposed on the wall of the liquid metal flow channel of a fusion reactor blanket. The parameters of the adhesion-diffusion process (pressure, temperature, hold-up time, and the physical properties of materials) are related to the strength characteristics of the resulting composite (incompleteness of the adhesion contact, adhesion energy, and energy and strength of cohesion). Results are illustrated by calculating the formation parameters of the multilayer metal-ceramic structure and its strength as applied to the fusion reactor liquid-metal blanket.     

Neutron flux distribution on the wall of toroidal controlled thermonuclear reactor devices with elongated cross section

The neutron flux distribution on the wall of a toroidal CTR device with strongly elongated cross section is calculated. On the inner and outer cylindrical walls (belt-pinch device) the flux distribution has a plateau region with a half-width equal to about the height of the plasma. The maximum flux is found on the outer cylinder and in the symmetry plane (z ₀=0). The neutron flux asymmetry and reductionη of the mean wall loading are determined. For standard data anη of 57% is computed. This is mainly due to the flux profiles on the cylindrical walls and does not depend sensitively on the toroidal curvature. For standard parameters the inner cylinder absorbs 22.6%, the outer cylinder 68.6% and the end plates together 8.8% of the total neutron emission. The corresponding values for a straight device with the same coil and plasma cross section are 44%, 44% and 12%. A reduction of toroidal curvature diminishes flux asymmetry between the inner and outer cylinders. The maximum flux and minimumη-value are obtained at a large torus radius equal to two times the coil width. For small aspect ratios (R _t W0.5) the neutron flux through the inner cylinder becomes so small that its interior may be filled with a material other than a blanket material, e.g. with an iron core.     

CFTER包层第一壁热工水力分析

简要描述了CFETR氦冷固态增殖包层的结构设计,介绍了包层第一壁的冷却结构。用ANSYS CFX程序对CFETR包层第一壁进行了热工水力分析。研究了如何获得第一壁的最佳出口温度,并保证第一壁结构材料的热负荷承受能力。讨论了通过改变冷却管道粗糙度和优化冷却管道布置两种方法对第一壁结构进行优化。结果表明,优化的冷却回路既满足了材料的许用温度要求,又满足了氦气的出口温度要求。     

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简要描述了CFETR氦冷固态增殖包层的结构设计,介绍了包层第一壁的冷却结构。用ANSYS CFX程序对 CFETR 包层第一壁进行了热工水力分析。研究了如何获得第一壁的最佳出口温度,并保证第一壁结构材料的热负荷承受能力。讨论了通过改变冷却管道粗糙度和优化冷却管道布置两种方法对第一壁结构进行优化。结果表明,优化的冷却回路既满足了材料的许用温度要求,又满足了氦气的出口温度要求。     

A note on the heating of the cold plasma blanket in a linear fusion reactor

On the basis of a simple model it is demonstrated that the Q-factor of present-day conceptual linear reactors is not enhanced by -particle heating of the cold plasma blanket surrounding the fusioning plasma column.     

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在ITER试验包层模块HC-SB TBM结构设计和热工计算分析的基础上,对包层模块中的重要部件第一壁做了优化分析。利用有限元分析软件ANSYS的可编程命令流模式,对HC-SB TBM第一壁前壁进行了温度和应力的数值模拟,在满足结构材料的许用温度和应力的前提下,给出了第一壁前壁的最佳设计方案。     

Network structure of thermonuclear reactions in nuclear landscape

Nucleosynthesis is a complex process in astro-nuclear evolution. In this work, we constructed a directed, multi-layer, nuclear reaction network, using the substrate-product method from a thermonuclear reaction database, JINA REACLIB. The network contained four layers, namely n-, p-, h-and r-, which correspond to the types of reactions involved in neutrons, protons,~4He and the remaining atomic particles, respectively. The degree values(i.e. numbers of reactions), for three layers of n-, p-, and h-,have a significant correlation with one another, and their topological structures exhibit a similar regularity. However, the r-layer has a more complex topological structure compared to the other layers; thus, its correlation of degree values with the other three layers is not as strong as that seen in the other layers. To analyze the motif structure of the nuclear reaction network, we used the software package mfinder. We identified the most frequent reaction patterns of the interconnections that occurred amongst the different nuclides. This work provides a novel approach to investigating the nuclear reaction network that prevails in the astrophysical context.     

氦气状态对超导托卡马克室温绝缘子电性能影响实验研究

为了解不同氦气状态对超导托卡马克室温绝缘子电性能的影响,建造了室温绝缘子氦气状态下电性能测试平台。利用该平台,在静态氦气和氦气流速为0.65g•s^-1状态下进行了室温绝缘子高电压-漏电流实验。实验结果表明,两种氦气状态下室温绝缘子均满足使用要求。     

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为了解不同氦气状态对超导托卡马克室温绝缘子电性能的影响,建造了室温绝缘子氦气状态下电性能测试平台.利用该平台,在静态氦气和氦气流速为0.65g·s?1状态下进行了室温绝缘子高电压-漏电流实验.实验结果表明,两种氦气状态下室温绝缘子均满足使用要求.     

Adiabatic wall focusing of intense ion beams for the ignition of thermonuclear microexplosions

It is shown that an intense can beam can be adiabatically and spherically symmetric focused onto a center of convergence by a Prandtl-Meyer flow inside a curved concave wall. The method can be extended to more than one wall and several beams and can be applied to the ignition of thermonuclear microexplosions.     

聚变堆液态包层准二维磁流体湍流模型研究

为研究聚变堆氚增殖包层中液态金属湍流磁流体动力学(MHD)效应,开发了一种新的准二维单方程 MHD 湍流模型,并进行了相关数值模拟程序的编制及验证。对于矩形管道中的准二维 MHD 湍流流动,三维流 动主要发生在哈德曼层中,中心的主流区呈现出二维流动。为了反映这种特殊的流动特征,新湍流模型在标准 k-ε 模型的基础之上去掉了传统的耗散项,代之以电磁耗散项来模拟湍流 MHD 效应。同时,采用 Bradshaw 假设来对 湍流涡粘系数进行模化。为验证该湍流模型是否合理,编制了相关数值模拟程序,并利用直接数值模拟(DNS)结 果对该程序进行了校正,数值模拟结果与 DNS 结果吻合较好。计算结果表明,该湍流模型可应用于聚变堆液态 包层 MHD 湍流流动的数值模拟。     

Computational simulation of thermal hydraulic processes in the core and fuel assembly in the liquid-metal fast-breader reactor in the porous medium approximation

The results of numerical simulation of the sodium coolant flow in the fuel assembly with partial blocking of its cross section are presented. A comparison of the results obtained with experimental data confirmed the operability of the APMod module intended for simulating heat exchange processes in cores and heat exchange equipment of promising nuclear reactors.     

Stability limits, structure, and relaxation of a mixed state in superconducting films with an edge barrier

The interval of external magnetic fields where a mixed state can exist in a superconducting film with a fixed value of the flux is determined. The equilibrium and reversible magnetization curves of the sample are calculated, and the dynamics of the magnetic relaxation in the film is described. Nonuniform deformation of the Abrikosov lattice is predicted. Pis’ma Zh. éksp. Teor. Fiz. 65, No. 5, 405–410 (10 March 1997)     

Modelling of a closed two-dimensional reactor bounded by a wavy wall

In this paper, we propose a model for a two-dimensional closed reactor bounded by a wavy wall. The left, right and top walls of the reactor are assumed to be flat surfaces while the bottom wall is a wavy surface. In order to formulate a model for such a reactor, we introduce a coordinate transformation into the dimensionless equations of a rectangular closed domain. Then the resulting equations illustrate the phenomena for a closed reactor bounded by a wavy wall. We solve these equations using the finite difference method. The astonishing results are that the intensity of streamlines and the maximum temperature within the reactor significantly increase with an increase of the number of waves in the bottom wall, the amplitude of waves and the Frank-Kamenetskii number. Converse characteristics are observed for higher values of the enlargement of a wave. Moreover, larger Rayleigh number induces stronger vortices in the flow field and reduces the maximum temperature. The Nusselt number at the bottom wavy wall is found to increase for higher values of the Frank-Kamenetskii number and the amplitude of a wave. A transition from the steady-state to the oscillatory convection is identified for a certain value of the Frank-Kamenetskii number. However, for a low value of the Rayleigh number, there occurs a transition from the steady-state to an explosion for increasing value of the Frank-Kamenetskii number. Results also demonstrate that the critical value of the Frank-Kamenetskii number, for which a transition from the steady-state to the oscillatory convection occurs, is higher for increasing values of the number of waves, the enlargement of a wave and the amplitude of a wave.     

Effects of a liquid lithium curtain as the first wall in a fusion reactor plasma

This paper explores the effect of a liquid lithium curtain on fusion reactor plasma, such curtain is utilized as the first wall for the engineering outline design of the Fusion Experimental Breeder （FEB-E）. The relationships between the surface temperature of a liquid lithium curtain and the effective plasma charge, fuel dilution and fusion power production have been derived. Results indicate that under normal operation, the evaporation of liquid lithium does not seriously affect the effective plasma charge, but effects on fuel dilution and fusion power are more sensitive. As an example, it has investigated the relationships between the liquid lithium curtain flow velocity and the rise of surface temperature based on operation scenario II of the FEB-E design with reversed shear configuration and high power density. Results show that even if the liquid lithium curtain flow velocity is as low as 0.5 m/s, the effects of evaporation from the liquid lithium curtain on plasma are negligible. In the present design, the sputtering of liquid lithium curtain and the particle removal effects of the divertor are not yet considered in detail. Further studies are in progress, and in this work implication of lithium erosion and divertor physics on fusion reactor operation are discussed.[第一段]     

Theoretical estimation of discontinuity flaw of adhesive contacts between multilayer elements of the liquid metal blanket in a fusion reactor

A technique developed for calculating the discontinuity flaw of an adhesive contact and the adhesion energy for two bodies makes it possible to take into account these effects in designing a multilayer cermet wall (insulating barrier) of the liquid-metal blanket in a fusion-type reactor. The technique is based on a model of a linearly elastic medium, in which strains are proportional to external forces, and on the assumption that any body in equilibrium possesses minimum internal potential energy. Expressions are derived for calculating the area of an adhesive contact between two bodies and their adhesion energy. Calculation data illustrate the dependence of these two parameters on the values of the Young modulus and Poisson’s ratio for various pairs of materials, including the most suitable materials for insulating barriers of liquid-metal blankets.     

On the possibility of developing the non-contact delivery system for cryogenic thermonuclear target transport to the IFE reactor

It is proposed to use the HTSC quantum levitation phenomenon in magnetic fields of various configurations to develop the systems of contact-free positioning and transport of cryogenic fuel targets (CFTs) to the focus of a high-power laser installation or the IFE reactor. The results are presented of a large cycle of experimental studies using YBa₂Cu₃O_7?x superconducting ceramics and permanent magnet guideways based on various combinations of permanentmagnets to develop “CFT-MAGLEV” delivery systems.