双滤膜法测~(222)Rn的进一步研究

本文介绍作者进一步研究双滤膜法测~(222)Rn 的工作结果。主要讨论了由过滤法测氡子体的基本方程推导出测定~(222)Rn 浓度的一般公式和衰变、扩散校正系数的计算公式。这些公式同时考虑了衰变和扩散对测定结果的影响。采用壁沉积方法,测得 RaA 的扩散系数 D=0.071cm~2/s。文中还分析了双滤膜法测~(222)Rn 的误差传递问题,结果表明,随着μ值(μ=0.06πDL/q,L 为采样管长度)的减小’D和取样流速 q 的误差对~(222)Rn 浓度测定结果的影响也显著减小。试从理论上解释该方法用于低μ条件时精密度和准确度都较高的特点。     

复合核反应及核反应的统计理论(续)

在核反应的统计理论中考虑了角动量效应而至今仍是卓有成效的理论是Hauser-Fesh-bach理论(以下简记为H-F理论)。1952年,W.Hauser和H.Feshbach在总结当时核反应成就的基础上提出复合核反应截面的计算公式。H-F理论不仅在实际应用中被广泛使用,而且对理论的发展也起了极其重要的作用。略去直接相互作用,并假定复合核的衰变和形成无关及道-道不相干,那么平均截面可以写成:     

用QCD理论研究D→π lv～l(l=e,μ)衰变过程

用光锥QCD求和规则计算D→π lv～l(l=e,μ)衰变过程的分支比.通过计算D→π跃迁形状因子f+Dπ(q2)和计算形状因子fDπ(q2),就能考虑轻子(e,μ)质量对分支比的影响,可分别计算D→π ev～e,D→π μv～μ衰变过程的分支比,并把理论计算与最近实验结果进行了比较,发现计算的分支比在实验数据误差范围之内.     

有源扩散方程的一种解和“双滤纸法”测氢的换算公式

文章从流速场中级联衰变下气载核素的扩散规律出发,提出了强吸附性壁圆管内氡子体扩散方程的完整定解问题,求出了等速分布廓线时的方程的精密解,弥补了C.W.Tan这部分工作的不足。引进了新的物理量m(μ),导出了等速分布条件下m(μ)与F(μ)的互换关系式。从测量氡子体的α计数出发,通过放射性平衡比m(μ)给出了“双滤膜法”测氡的换算公式。由J·W·Thomas的精密实验数据,取镭-A扩散系数D=0.07cm~2·s~(-1)时,理论与实验十分吻合。     

用QCD理论研究D→πl■(l=e,μ)衰变过程

用光锥QCD求和规则计算D→πl~vl(l=e,μ)衰变过程的分支比。通过计算D→π跃迁形状因子fD+π(q2)和计算形状因子~fDπ(q2),就能考虑轻子(e,μ)质量对分支比的影响,可分别计算D→πe~ve,D→πμ~vμ衰变过程的分支比,并把理论计算与最近实验结果进行了比较,发现计算的分支比在实验数据误差范围之内。     

用闪烁计数器测定岩石样品中的镭含量

1.引言在铀矿普查、勘探的各个阶段,精确地测定镭在岩石样品中的含量,是确定一个矿区内放射性平衡与否、射气扩散程度等一系列问题的不可缺少的一项工作。目前测定岩石样品中镭含量的方法有:射气法和脉冲法。射气法是假定镭和氡之间存在着放射性平衡,利用氡气衰变时所放出的α射线在电离室中产生的电离电流,与引入电离室的     

不同级钚材料的衰变放热功率计算分析

钚材料中放射性核素会不断衰变并释放能量,改变钚材料及周围部件的温度。为研究不同级钚材料在其整装存储及运输过程中衰变放热功率随时间的变化规律,依据不同级钚材料的放射性核素组分,在分析核素级联衰变规律的基础上,并在物理模型中考虑衰变时的能量分支比,计算得到了武器级钚、反应堆级和混合级钚材料中各核素的衰变放热功率和总热功率随时间的演变规律。计算结果表明,1 kg不同级的钚材料,其衰变放热功率最大的是混合级钚,放热最少的是武器级钚;武器级钚材料衰变放热功率主要来自于~(239)Pu,而反应堆级与混合级钚材料的衰变放热功率主要来自于~(241)Pu和~(238)Pu。三种不同级钚材料中,~(242)Pu的衰变放热功率均很小。考虑能量分支比后,可更准确地计算给出钚材料的衰变热功率。     

大气中(气土)浓度的测定方法

(气土)(~(220)Tn)是~(232)Th子代核素~(224)Ra的衰变产物,它是氡(~(222)Rn)的同位素,属惰性气体。它们的衰变产物为α、β、γ辐射源。土壤中含有天然放射性元素~(232)Th,当它衰变产生(气土)气时,即从土壤中扩散到大气中。由于~(220)Tn半衰期很短(54.5s),所以只有离地表6cm厚的那层土壤产生(气土)气才能释放出来。释放率和土壤的湿度有很大关系,一般情     

用于氡气测量装置的探测器总成的设计与实现

介绍了一种基于静电扩散法的氡气测量装置的探测器总成,它采用由硅胶干燥器、双层滤膜、高压静电收集衰变室和微型气泵构成的采样气路收集氡,利用金硅面垒探测器,电荷灵敏放大器对衰变室内氡的子体进行探测,并配有峰值保持电路.     

大气中(气土)子体α潜能值的测量

在处理含钍矿石的厂矿中,(气土)子体对人主要危害是吸入呼吸道内对人体产生内照射,其中主要是由(气土)子体在衰变过程中放出的α粒子的能量所致。(气土)子体的α潜能系指单位空气中的(气土)子体原子完全衰变到ThD过程中所释放的α粒子能量的总和。它是直接反映被(气土)子体沾染的空气危害程度的一个有用指标。因此测量(气土)子体的α潜能值比测量它的浓度值更具有实     

Atomic Diffusion Behavior in W/Cu Diffusion Bonding Process

Tungsten and copper are critical materials which are used in the nuclear fusion reactor, however thermal stresses would produce at the bonding interface during W/Cu bonding and service. Diffusion layer of diffusion bonding is similar to functionally graded materials, so the thermal stresses of W/Cu bonding can be reduced by the diffusion bonding. The process of W/Cu diffusion bonding was simulated by molecular dynamics, atomic diffusion behavior of W/Cu diffusion bonding was studied, diffusion coefficient and radial distribution function were obtained. Diffusion mechanism of W/Cu diffusion bonding is that diffuses along the defects surface of crystal, thickness of diffusion layer and disordered degree of atoms rose when the temperature and diffusion time are increased.     

核级石墨微观孔隙有效扩散系数研究

有效扩散系数是描述石墨内部扩散传质的重要参数,传统经验公式中的单一平均孔径假设无法反映石墨内部复杂的孔隙孔径分布规律及其对扩散的影响,现有核级石墨的有效扩散系数计算公式与实验结果相差较大。考虑到受Knudsen扩散影响,并根据核级石墨微观孔隙孔径分布规律及扩散理论将孔径范围分为两类,从而对有效扩散系数计算公式进行了修正。采用压汞仪对IG110核级石墨未氧化及不同温度下等温氧化样品进行了孔径分析,采用本文修正公式计算了有效扩散系数并与实验测量结果进行了比较。同时对失重率、温度和压力对有效扩散系数的影响进行了讨论。结果发现,修正公式计算结果与核级石墨扩散系数的实验结果相符,提高了核级石墨有效扩散系数的计算精度。有效扩散系数随失重率的增加而升高,失重率低于20%时增长明显。有效扩散系数与温度呈0.528次方关系,与压力大致呈-0.33次方关系。     

福建惠安核电厂址大气扩散野外示踪试验研究

描述了于2002年夏季在福建惠安核电厂址进行的SF6示踪试验及其主要结果。共进行了15次SF6示踪试验,其中释放高度为70m的五次,30m的六次,10m的四次。天气类型若按?T-U分类,B,C,D,E类天气分别出现3,2,9,1次,若按?T分类,B,D,E类天气分别出现1,11,3次。每次约取50个样品,最远取样点距释放SF6的铁塔15km左右。基于这次试验给出了适用于该厂址各类天气条件下的扩散参数,最后把试验推荐的扩散参数与P-G曲线,Briggs扩散参数以及以往在该厂址进行的湍流测量与风洞模拟实验推荐的扩散参数进行了比较分析。     

Measurement of Thermal Neutron Cross Section of 137Cs(n, γ)138Cs Reaction

A calculational model for a modified diffusion coefficient has been developed to incorporate the neutron streaming effect in heterogeneous low-density channels accurately into diffusion theory calculations. The model uses a supercell, and the axial and radial diffusion coefficients of the heterogeneous inner cell are so defined that they can reproduce Benoist's axial and radial diffusion coefficients of the supercell when the diffusion coefficient of the outer cell is given as 1/3 Σ_tr . In the case of the axial diffusion coefficient, the axial buckling effect is taken into account by modifying the neutron path length within the streaming channel in calculating the collision probabilities. This model has been applied to an RZ fast reactor Core model with a gas expansion module (GEM). By using the axial diffusion coefficient obtained with the presented model, calculational error of GEM worth was reduced to less than 1/7 compared to the formula of Rowlands and Eaton.     

H and D depth profiles in implanted and laser-annealed beryllium

The thermodynamic properties of H and D implanted in Be to different fluences have been investigated by laser flash desorption. From the evolution of the H and D depth profiles following laser annealing, different detrapping/diffusion processes in matter are proposed. The experimental results were compared to those obtained from a finite element time resolved simulation code. Two different processes depending on the H or D fluence can be inferred: at low fluence, a 1.7 eV/molecule detrapping energy and a fairly high effective diffusion coefficient have to be involved, while at high fluence the detrapping energy is ≤1 eV/molecule and an extremely rapid migration have to be considered. The transition between these two regimes corresponds approximately to the fluence for which blistering becomes detectable.     

Determination of Cell Averaged Diffusion Constants Based on Transport/Diffusion Perturbation Theory

A unified definition for cell-averaged diffusion constants has been established on the basis of transport and/or diffusion perturbatlon theories. The diffusion constants are derived by equating each component of reactivities obtained by transport theory for a heterogeneous cell to a corresponding component of reactivities by diffusion theory for a homogenized cell. The derived diffusion constants are applied to infinite uniform lattices and heterogeneous lattices composed of different cells. In infinite lattices the present diffusion constants are compared to the conventional flux-weighted cross sections and Benoist's anisotropic diffusion coefficients. In heterogeneous lattices they are compared with Rowlands-Eaton cross sections and the extended Benoist's diffusion coefficient. The present formula is applied to a heterogeneous slab lattice. It reveals that the present method gives a more accurate result for k _eff compared to the case with the conventional diffusion coefficient defined by D= 1/3Σ_tr or the extended Benoist's diffusion coefficient together with the conventional flux-weighted cross sections.     

Chemical diffusion coefficient calculation of U3+ in LiCl-KCl molten salt

Self-diffusion coefficient denotes the intrinsic diffusion of elements without the chemical gradient; generally, it is different from the chemical diffusion coefficient that is used in Fick's law. However, the self-diffusion coefficient can be converted to the chemical diffusion coefficient by considering the concentration-dependent activity coefficient of solute. In this study, the multiple time origins method was applied to calculate the self-diffusion coefficient of U³⁺ in LiCl-KCl eutectic salt at different temperatures and concentrations. The chemical diffusion coefficient was obtained based on the calculated results and thermodynamic theory. Calculated results show that self-diffusion coefficient decreases with concentration however chemical diffusion coefficient indicates to change little initially but appears to increase followed by decrease later within the concentration range of 0–3 at%.     

Automatic Plotting of Isoflux Contours with On-Line Printer

The effect of neutron streaming upon the neutron multiplication factor in a fast critical assembly FCA-VI is estimated by considering the anisotropy of the diffusion coefficient. In this paper, the Benoist formula is adopted to obtain the diffusion coefficient. In his original expression, many effects such as those of neutron angular distribution, multiple collision (correlation of different neutron passes) and finiteness of lattice system are included. In order to estimate these effects, the generalized first-flight collision probability method is adopted as in the previous paper, and an improvement is brought over the previous method so as to calculate the effective diffusion coefficient in a practical slab lattice cell which is asymmetric about the center of the cell.

Using the method of calculation described above, the anisotropic effect of neutron streaming in the lattices TA, TB, TC and TD used in the FCA VI-1 assembly is estimated. The effect of anisotropy of the diffusion coefficient upon the multiplication factor for the TA, TB, TC and TD lattices is found to be ?0.156, ?0.181, ?0.242 and ?0.330% δk/k, respectively.

Usually, the effects of neutron distribution, multiple collision and anisotropic scattering are neglected in evaluating the diffusion coefficient when using the Benoist formula. Among these factors, the effect of multiple collision of neutrons has the largest effect upon the diffusion coefficient and upon the neutron multiplication factor. For the TA lattice, 30% of the overall effect of anisotropy is attributable to multiple collision.     

Anisotropic Thermal Expansion of Uranium-Refractory Metal-Carbides: UWC2 and UMoC2

The anisotropic diffusion coefficient has been calculated in a cylindrical cell with use made of the integral transport theory. The previous method⁽¹⁾ of calculating the diffusion coefficient requires much computer time to evaluate the generalized first-flight collision probabilities between two mesh points for a square cell. To circumvent this drawback, we introduce new calculation methods for determining the anisotropic diffusion coefficient in a cylindrical cell. Two methods are proposed–one uses the diffusion theory in the outermost moderator region of a cell; the other adopts the integral transport theory in that region as well. For the latter method, a new boundary condition is introduced for the cell surface, which, in the present problem, supersedes the usual isotropic return boundary condition. Using these two methods, the anisotropic diffusion coefficient can be evaluated with very short computer time. Moreover, an analytic expression is obtained for the special case where a cell is composed of a fuel and a moderator.     

一种新的放射性核素迁移弥散系数计算方法

研究放射性核素在饱和被压实缓冲/回填材料中的迁移对于核废物处置具有十分重要的意义,为了用数学模拟的方法准确地对放射性核素迁移进行描述和预测,首先必须精确地求出有关的放射性核素迁移参数——弥散系数、吸附系数等,其中最重要之一就是弥散系数。目前确定放射性核素在被压实缓冲/回填材料中迁移弥散系数的方法主要有经验公式法和示踪实验。本工作结合放射性核素铀迁移的室内实验,应用概率理论计算了被压实缓冲/回填材料中核素迁移水动力弥散系数,讨论了被压实缓冲/回填材料水动力弥散系数和地下水流速对放射性核素在被压实缓冲/回填材料中迁移的影响。最后总结分析了具体的实现步骤。