The Ignition Requirements of the Degeneracy Microspheres of Deuterium Helium-3 Mixture with Low-Radioactive

This paper examines the burn characteristics for inertial confinement D/³ He fuel pellets with different concentrations of Helium-3. It is shown that the Helium-3 relative density of the fuel mixture plays a significant role in determining the burn characteristics and fuel gain. In spite of the safety of the plasma degeneracy of D/³ He fuel with fraction of y?=?0.2 (y: Helium-3 content parameter), ignition of fuel is impossible. In design fuel extra to safety should be considered fractional burn-up and fuel gain. The main contribution of this research is to show that the plasma degeneracy of equimolar mixture of D/³ He fuel lowers the ignition temperature and increases fuel gain. The results indicate that a $n_{D} /n_{{^{3} He}}$ ?≤?0.3 is difficult to ignite reasonable driver energy. A fuel gain of 378 can be obtained with a D/³ He fuel with fraction of y?=?0.33, and areal density (ρR) of 12 g/cm². It is found that the fuel gain of an equimolar D/³ He fuel at temperature of 70?keV and ρR value of 8.5 g/cm² is 480. This value gain is higher by about 22% than the case of the pellets (y?=?0.33).     

AFA 3G燃料棒芯块与包壳间相互作用分析

介绍了大亚湾核电站18个月换料策略下,在Ⅱ类工况瞬态期间AFA 3G燃料棒芯块与包壳间相互作用（PCI）的分析和预测。文中给出了PCI技术限值,介绍了Ⅱ类工况瞬态分析和热力机械分析的分析方法和程序,并给出了基荷运行、基荷加一次调频运行、负荷跟踪运行以及延伸低功率运行时的负荷过量增加、功率状态下控制棒失控抽出和未检测到的掉棒3种瞬态的PCI主要计算结果和结论。     

Effect of Fuel Pellet Eccentricity with Cladding on Fuel Rod Thermal Behavior under Reactivity Initiated Accident Condition

Fuel rod behavior under Reactivity Initiated Accident (RIA) conditions has been studied in the Nuclear Safety Research Reactor (NSRR), JAERI. In the experiments, cladding thermal behavior was observed to be influenced by the fuel pellet eccentricity to produce large azimuthal temperature variation in the cladding. The maximum azimuthal cladding temperature difference was measured to be as large as 150°C by thermocouples attached to opposite sides of the cladding around the circumference, though the thermocouples did not always detect the maximum temperature difference around the circumference. The actual temperature differences in the fuel rods subjected to less than 290 cal/g?UO₂ were estimated to be 350°C at maximum based on metallographies. A simple calculation considering gap conductance variations also showed that the maximum temperature difference became 350°C under fully eccentrical condition in the fuel rod subjected to 260 cal/g?UO₂. Moreover, as the rod damage such as cladding deformation, melting and failure occurs unevenly around the circumference due to the fuel pellet eccentricity in general, the fuel pellet eccentricity should influence the fuel rod failure under RIA conditions.     

Development of an Engineering Model of Fuel Pellet Sintering in Multi-Zone Furnaces

Atomic Energy - An engineering model for sintering of fuel pellets is presented. The model is based on a previous, fully developed, mathematical model, which was implemented by the method of finite...     

Neutronics Optimization of Tritium Breeding Blan-ket for the FDS

Neutronics optimization calculations have been performed for the tritium breeding blankets with solid ceramic breeder Li2O and liquid eutectic breeder Li17Pb83,respectively,based on a 2-D geometrical configuration using the Monte Carlo neutron-photon transport code MCNP/4B.The effects of beryllium.^6Li enrichment and various structural materials on Tritium Breeding Ratio have been systematically analyzed.     

双功能液态锂铅包层氚增殖性能分析

双功能液态锂铅(DFLL)包层作为一种高性能的产氚包层,是中国聚变工程实验堆(CFETR)的候选包层之一。氚增殖比(TBR)是产氚包层核心设计参数之一,是评估聚变堆氚自持性能的重要指标,有必要对其进行详细分析。本文介绍了DFLL包层氚增殖性能数值分析与实验验证工作。其中数值分析采用中子输运设计与安全评价软件系统SuperMC建立了全堆三维中子学模型,计算分析了包层不同位置处的TBR值,并对影响包层氚增殖性能的相关因素,如第一壁材料、钨护甲、包层增殖区厚度、6 Li富集度等进行了敏感性分析及参数优化;实验验证工作利用强流聚变中子源HINEG,开展了DFLL中子学实验模块不同位置产氚率(TPR)测量。研究结果显示,经过优化的DFLL包层TBR设计参数可达到1.208,满足CFETR第一阶段的氚自持要求;实验结果与理论计算结果的最大偏差为8%以内符合,实验结果的测量不确定度在2σ内优于9.8%。     

Effect of Lithium Enrichment on the Tritium Breeding Characteristics of Various Breeders in a Fusion Driven Hybrid Reactor

Selection of lithium containing materials is very important in the design of a deuterium–tritium (DT) fusion driven hybrid reactor in order to supply its tritium self-sufficiency. Tritium, an artificial isotope of hydrogen, can be produced in the blanket by using the neutron capture reactions of lithium in the coolants and/or blanket materials which consist of lithium. This study presents the effect of lithium-6 enrichment in the coolant of the reactor on the tritium breeding of the hybrid blanket. Various liquid–solid breeder couples were investigated to determine the effective breeders. Numerical results pointed out that the tritium production increased with increasing lithium-6 enrichment for all cases.     

燃料元件功率瞬态试验氦-3回路中氚阱设计

在燃料元件堆内功率瞬态试验中,为净化氦-3气体吸收中子产生的氚,保证试验的安全性,需设计一个用于捕集氚的装置——氚阱。选择海绵钛作为贮氚金属。原型容器的设计主要依据氚的产量、氚钛化学反应、温度、压力、还有氚衰变氦释放等因素。总体结构采用内加热形式的双层包套式不锈钢压力容器,可减小热损失和氚的渗透量。本文同时也介绍了氚阱的结构、传热、屏蔽和密封等的分析结果。     

低密度UO2燃料芯块的制备及微观结构

本文介绍了在UO_2粉末中加入造孔剂制备低密度UO_2燃枓芯块的方法。试验结果表明,加入4wt％草酸铵可获得85.31%TD的烧结块,其开口孔率为0.69%。加入2wt%聚乙烯醇可获得85.10%TD烧结块,其开口孔率为1.16%。而且,它们的孔隙形态、尺寸及分布都是令人满意的。两者再烧结后芯块密度分别增加了0.22%TD和0.30%TD,晶粒尺寸分别为14.3μm和16.1μm。     

燃料棒芯块中Kr、Xe的低温释放机理

在Wise反冲机理微观模型的基础上,考虑芯块倒角的影响,给出了倒角表面平均反冲效率的计算模型;击出机理参考Olander的理论;由此建立了一个更为精细的裂变气体低温释放微观模型.使用新建模型进行计算的结果显示,倒角表面的平均反冲效率约为圆柱体芯块表面的两倍;当倒角的表面积与圆柱体芯块表面积相比不可忽略时,裂变气体反冲释放份额的计算应考虑倒角的影响.     

3He对 LaNi5储氚性能影响的第一性原理

基于第一性原理的密度泛函理论研究LaNi5储氚过程中T衰变为3He前后晶体的几何结构和能量变化,计算得到了在平衡态时3He在储氚的LaNi5合金中的最可几占位为八面体位置和十二面体位置。进一步分析了衰变前后的材料能带结构、电子态密度(DOS)分布。氦的惰性不溶使LaNi5合金晶格膨胀和电子态密度分布发生变化是影响LaNi5储氚过程中坪台压降低、斜坪增大的主要原因。在氦原子周围形成的深势阱是形成氚尾效应的主要原因之一。     

Impact of Solid Breeder Materials on Tritium Breeding in a Hybrid Reactor

Tritium breeding ratio (TBR) is one of the important parameters in design of a Deuterium–Tritium (DT) driven hybrid reactor. Therefore, selection of tritium breeder materials to be used in the blanket is very crucial. In this study, tritium breeding potential of the solid breeders, namely, or in a (DT) fusion driven hybrid reactor fuelled with or was investigated. For this purpose in addition to these solid breeders, different types of liquid breeders, namely natural lithium, Flibe, Flinabe and were used to examine the tritium breeding behavior of liquid–solid breeder couple combinations. Numerical calculations were carried out by using Scale 4.3. According to numerical results, the blanket with fuel using natural lithium as coolant and as solid breeder had the highest TBR value.     

放射性裂变产物由燃料芯块释放到一回路的影响因素研究

采用PROFIP5程序分析燃料棒线功率密度、衰变常数和破口尺寸等对放射性裂变产物释放的影响。结果表明:当燃料棒中心温度低于1000℃时,裂变产物的释放份额与燃料棒温度无关;当燃料棒中心温度高于1000℃时,燃料棒温度越高,裂变产物的释放份额越大;燃料棒线功率密度越高,衰变常数对释放份额的影响越明显。     

Temperature and Concentration Dependence of Tritium Release Behavior from Solidified LiF-PbF2 Pellet Irradiated by Thermal Neutron

Thin pellets of the LiF-PbF₂ system with no porosity were irradiated by thermal neutron. Then release experiment of tritium produced in the pellets was carried out at some constant temperatures. Thus diffusion coefficients of tritium in the LiF-PbF₂ system were estimated to obtain an activation energy of diffusion, which was found to be 0.51 eV at LiF mole fraction of 0.467. It was also observed that decrease of LiF concentration in the pellet brings increase of diffusion coefficient of tritium.     

燃料组件由AFA 2G改为AFA 3G对反应堆堆内构件地震响应的影响

建立燃料组件为AFA 2G和AFA 3G两种堆芯结构的反应堆非线性地震分析模型,采用ANAYS软件进行地震情况下的非线性时程动力分析研究,并对分析结果进行对比。结果表明:燃料组件由AFA 2G变为AFA 3G不用对反应堆堆内构件进行重新分析评定,只需要对燃料组件本身进行重新分析评定。     

Impact Analysis of Helium Cooled Solid Blanket Structures on the Tritium Breeding Performance in CFETR

Chinese Fusion Engineering Test Reactor (CFETR) is a test tokamak reactor to bridge the gap between ITER and future fusion power plant. As its objectives are to demonstrate generation of fusion power and to realize tritium self-sufficiency, the tritium breeding ratio (TBR) is a key design parameter. In the blanket design and optimization, the structures such as the first wall (FW), cooling plate (CP), stiffening plate (SP), cap and some other design parameters in detailed 3-D model have significant impacts on the tritium breeding performance. Based on a helium cooled solid breeder blanket option for CFETR, the impact analysis of the helium cooled solid blanket structures on tritium breeding performance was performed in this paper. Firstly, the detailed 3D neutronics model was built by using of a CAD to Monte Carlo Geometry conversion tool McCad. Then based on the detailed 3D neutronics model, the impact analyses of the blanket structures on tritium breeding performance were carried out, which include the FW, CP, SP, cap and side wall. By the sensitivity study of the blanket structures on the TBR, it gave the TBR variation trend and references for the blanket design and optimization.     

GDT聚变中子源氚燃料循环初步设计与分析

基于GDT概念的聚变中子源具有等离子体易实现稳态运行、结构简单紧凑、技术实现难度较低、易于升级与维护、氚消耗量低等特点,其建成后可作为聚变结构材料或部件的测试平台。由于氚在真空室内的燃烧份额很低,所以有必要为该装置建立安全而高效的闭式氚燃料循环系统,以提高氚燃料的经济性。本文首先分析GDT在氚燃料循环方面的特点,然后参考最新的ITER和DEMO氚燃料循环设计,旨在建立匹配的氚燃料循环系统,以满足GDT聚变中子源稳定运行的燃料需求。根据物料注入方式、氚处理系统功能、循环回路等方面的不同,分别提出了三套氚燃料循环方案GDT—TFC1、TFC2和TFC3,并分析它们在系统氚盘存量、氚投料量方面的差异。从氚燃料经济性的角度考虑,为该装置氚燃料循环方案的选取提供了一定的参考。     

Models of Ceramic Tritium Breeding Zones in the Blanket of a Thermonuclear Reactor

The development, performed in the 1980s–1990s, of models of tritium breeding zones for blankets of thermonuclear reactors, based on the use of ceramic lithium-containing materials, is described. 5 figures, 1 table.