材料中氢同位素的多维扩散行为计算

研究了氢同位素在材料中多维扩散行为的有限差分计算方法。对二维扩散问题的交替方向隐式有限差分解法进行了推导,并用数值解和乘积法求出的解析解计算了圆柱体不锈钢样品一次充氘的浓度分布,两者的计算结果相近。无论是解析方法,还是数值方法,多维扩散问题都可以分解为多个较简单的一维扩散问题。     

质谱法测量碳同位素丰度在气体扩散法分离乙醇中的应用

乙醇是扩散分离碳同位素的一种可行的介质,为得到气体扩散法分离乙醇的分离系数,开展元素分析-同位素比质谱法(EA-IRMS)测量乙醇中碳同位素丰度在气体扩散分离实验中的应用研究。通过文献调研,本研究优化了乙醇样品的制备流程,发展了EA-IRMS用于乙醇碳同位素丰度测定的方法,进行了稳定性测试,实现了对乙醇样品碳同位素丰度的测量。基于气体扩散法的分离实验,获取多次分离实验中精料乙醇和贫料乙醇的碳同位素丰度,经公式推导可计算得到乙醇扩散分离碳同位素的基本全分离系数。本研究为未来开展以乙醇为介质扩散分离碳同位素实验提供了分析基础。     

质谱法测量碳同位素丰度在气体扩散法分离乙醇中的应用

乙醇是扩散分离碳同位素的一种可行的介质,为得到气体扩散法分离乙醇的分离系数,开展元素分析-同位素比质谱法(EA-IRMS)测量乙醇中碳同位素丰度在气体扩散分离实验中的应用研究。通过文献调研,本研究优化了乙醇样品的制备流程,发展了EA-IRMS用于乙醇碳同位素丰度测定的方法,进行了稳定性测试,实现了对乙醇样品碳同位素丰度的测量。基于气体扩散法的分离实验,获取多次分离实验中精料乙醇和贫料乙醇的碳同位素丰度,经公式推导可计算得到乙醇扩散分离碳同位素的基本全分离系数。本研究为未来开展以乙醇为介质扩散分离碳同位素实验提供了分析基础。     

锕系元素的胶体迁移行为

本文在文献调研的基础上,论述了在进行放射性废物处置安全评价时研究胶体迁移行为的重要性,讨论了锕系元素真胶体和假胶体在有关介质中的形成及其对核素在地质介质中迁移的促进作用,介绍了有关锕系元素胶体迁移行为的模式化研究。     

曲网格下的厚扩散极限中子输运模拟研究

离散纵标法作为求解厚扩散极限中子输运问题的重要方法之一，其常用的空间离散格式，如有限差分格式极易在光学厚介质中产生数值扩散，并且粗网格精度不足和难以适配复杂几何等问题使得离散纵标法的应用具有一定的局限性。本研究采用伽辽金方法推导弱形式或变分形式的离散纵标方程，基于间断有限元思想构造高阶曲网格下的拉格朗日有限元基函数，建立中子输运方程的高阶间断有限元离散格式。选取了构造解算例、国际原子能机构（IAEA） EIR-2基准题和厚扩散极限算例进行建模与输运计算，对该空间离散格式的计算精度、收敛性进行了测试验证并分析了其厚扩散极限特性。数值结果表明，多介质问题中高阶间断有限元格式的计算结果与基准值相对误差小于1%，且在曲网格下也具有较高的计算精度和符合预期的收敛速度。该离散格式可有效解决曲网格下的厚扩散极限中子输运问题，具有较好的数值特性，且在光学厚扩散极限下具备扩散极限渐近保持性质。     

惰性气体核素^127Xe制备实验研究

在军控核查研究气体在环境中的沉积、扩散等的项目中，为寻找1种气体核素示踪方法，本工作对放射性气体核素^127Xe的制备方法进行研究。在反应堆中对盛装在玻璃管中的普通氙辐照96h，经一定时间冷却后，将辐照产物吸附到处于液氮温度下的特制源盒中，20min后，待Xe气体在源盒中达到均匀分布再进行γ能谱测量，以获得^127Xe的准确活度值。实验结果证实，应用上述方法制备放射性气体示踪核素^127Xe是可行的。     

惰性气体核素127Xe制备实验研究

在军控核查研究气体在环境中的沉积、扩散等的项目中，为寻找1种气体核素示踪方法，本工作对放射性气体核素¹²⁷Xe的制备方法进行研究。在反应堆中对盛装在玻璃管中的普通氙辐照96h，经一定时间冷却后，将辐照产物吸附到处于液氮温度下的特制源盒中，20min后，待Xe气体在源盒中达到均匀分布再进行γ能谱测量，以获得¹²⁷Xe的准确活度值。实验结果证实，应用上述方法制备放射性气体示踪核素¹²⁷Xe是可行的。     

核事故放射性气体扩散及辐射剂量模拟研究

利用修正的高斯烟团模型来简化早期核事故扩散问题,将修正后结果与CALPUFF软件模拟结果对比分析,误差在可接受范围内。根据放射性气体扩散模拟及辐射剂量计算,开发了可视化操作界面,给定初始参数便可简单快速计算得到放射性扩散核素浓度随时间分布以及辐射剂量影响,可为核事故应急预案制备提供依据。     

非线性迭代半解析节块方法在压水堆燃料管理计算中的应用

利用半解析节块法的非线性迭代计算方法求解多维多群中子扩散方程。数值结果表明 ,这种非线性迭代半解析节块法具有较高的精度 ,并且在计算效率上比传统方法有很大的提高。将这种方法应用于SIMULATE E中 ,研制了压水堆燃料管理计算程序CSIM 3B ,对秦山核电厂第一循环进行了跟踪校核计算 ,取得了较好的计算结果     

TiD_(1.92)热解析的动力学行为研究

采用热分析和理论计算的方法对TiD1.92粉末的解析行为进行了研究。计算的TiD1.92粉末有3类解析峰,均与TiD1.92解析中发生相变导致的氘扩散速率变化有关。球形颗粒模型的解析与平板颗粒模型的解析因其相变和扩散机制不同导致β→α相变解析峰表现出一定的差异。TiD1.92粉末的热分析结果与平板颗粒模型的计算结果完全一致,其中δ相和β相钛氘化物的解析由表面反应控制,β→α相变阶段的解析由氘在α相的扩散控制,实验获得氘在钛表面的解析活化能为152.8kJ/mol以及氘在α相中的扩散活化能为68.6kJ/mol。     

节块展开法求解对流扩散方程的稳定性和数值耗散特性分析

本文研究了节块展开法求解对流扩散方程的稳定性和数值耗散特性。通过离散方程精确解和数值实验方法分析不同阶节块展开法的稳定性和数值耗散特性,并将其与有限体积法中的中心差分和一阶迎风格式进行对比。结果表明:偶数阶节块展开法的稳定是有条件的,即Peclet数(Pe)小于限值,且Pe限值会随展开阶数的增大而增大,其稳定性范围和精度均优于中心差分格式;奇数阶节块展开法是无条件稳定的,但随Pe的增大,数值耗散增大、计算误差增大,且当Pe大于一定值后,产生的数值耗散大于一阶迎风格式。     

核电厂放射性废物重整流态化数值模拟研究

核电厂排放的放射性废物高温重整过程中会以流化态的形式存在,为获取这个过程中的详细参数,设计出更优秀的运行条件,提出了一种新的核电厂放射性废物重整流态化数值模拟方法。该设计数值计算模型建立了气-固流体力学控制方程以及湍流模型;建立了核电厂放射性有机化学废物几何模型、对象几何模型,并划分网格结构,设置边界初始条件。通过数值计算研究不同高径比对颗粒的径向速度、径向固含率、径向气含率的影响。计算结果表明,高径比为1.0时,流化床中气-固颗粒的流化效果最好。      

Research on GPU-accelerated algorithm in 3D finite difference neutron diffusion calculation method

In this paper, the adaptability of the neutron diffusion numerical algorithm on GPUs was studied, and a GPU- accelerated multi-group 3D neutron diffusion code based on finite difference method was developed. The IAEA 3D PWR benchmark problem was calculated in the numerical test. The results demonstrate both high efficiency and adequate accuracy of the GPU implementation for neutron diffusion equation.     

Monte-Carlo simulation of a stochastic differential equation

For solving higher dimensional diffusion equations with an inhomogeneous diffusion coefficient,Monte Carlo (MC) techniques are considered to be more effective than other algorithms,such as finite element method or finite difference method.The inhomogeneity of diffusion coefficient strongly limits the use of different numerical techniques.For better convergence,methods with higher orders have been kept forward to allow MC codes with large step size.The main focus of this work is to look for operators that can produce converging results for large step sizes.As a first step,our comparative analysis has been applied to a general stochastic problem.Subsequently,our formulization is applied to the problem of pitch angle scattering resulting from Coulomb collisions of charge particles in the toroidal devices.     

Measurement of Average Cross Section for 238U(n, 2n)237U Reaction

Accurate solution of the group diffusion equations for PWR cores requires explicit treatment of the non-homogeneous macroscopic parameters within each fuel assembly. It is argued that the response matrix approach is a convenient method to handle this problem provided all matrix elements for the non-homogeneous assemblies can be computed. This so called local problem is solved in this paper by a perturbation algorithm which leads to sensitivity coefficients for the power series expansions of the response matrix elements. A numerical study for 2 representative assemblies of the Indian Point Unit No. 2 (IP2) reactor is carried out and response matrices obtained by the perturbative method are compared with values computed by a finite difference program.     

Modeling the diffusion yield of radioactive fission products from uranium dioxide fuel

The numerical aspects of a systematic solution of the problem of diffusion and yield of radioactive fission products from a homogeneous sphere, simulating a uranium dioxide fuel kernel, with realistic boundary conditions are discussed. The numerical scheme is based on a one-group method of calculating the production and radioactive mutual transmutations of fission products in combination with the standard expansion of the radial dependence of the concentration in terms of the eigenfunctions of the Laplace operator. It is demonstrated on illustrative examples that the approach is highly economical.     

Early construction and operation of the highly contaminated water treatment system in Fukushima Daiichi Nuclear Power Station (IV) - Assessment of hydrogen behavior in stored Cs adsorption vessel

Hydrogen diffusion behavior in a cesium adsorption vessel is assessed. The vessel is used to remove radioactive substance from contaminated water, which is proceeded from Fukushima accident. Experiment and numerical calculation are conducted to clarify the characteristics of natural circulation in the vessel. The natural circulation arising from the temperature difference between inside and outside the vessel is confirmed. We develop an evaluation model to predict the natural circulation and its prediction agrees well with the results obtained by the experiment and the calculation. Using the model, we predict steady and transient behavior of hydrogen concentration. Results indicate that hydrogen concentration is kept lower than the flammability limit when the short vent pipe is open.     

Chemo-mechanical coupling behaviour of leached concrete: Part II: Modelling

The paper is concerned with a coupled chemo-mechanical model describing the interaction between the calcium leaching and the mechanical damage in concrete materials. On the one hand, the phenomenological chemistry is described by the nowadays well-known simplified calcium leaching approach. It is based on the dissolution–diffusion process together with the chemical equilibrium relating the calcium concentration of the solid's skeleton and the calcium in the pore solution. For concrete, a homogenization approach using asymptotic expansions is used to take into account the influence of the presence of the aggregates leading to an equivalent homogeneous medium. On the other hand, the continuum damage mechanics is used to describe the mechanical degradation of concrete. The modelling accounts for the fact that concrete becomes more and more ductile as the leaching process grows. The model also predicts the inelastic irreversible deformation as damage evolves. The growth of inelastic strains observed during the mechanical tests is described by means of an elastoplastic-like model. The coupled nonlinear problem at hand is addressed within the context of the finite element method. And finally, numerical simulations are compared with the experimental results of first part of this work.     

Basic Characteristics of Centrifuges, (IV)

A method of numerically solving the convection-diffusion equation is presented for a binary isotopie gas mixture in the axisymmetric velocity field. A modified Newton's method is employed to perform the numerical integration without the assumptions that the pressure can be estimated from the rigid rotation model and the temperature of gas is uniform. A suitable form of the finite difference equation gives a computationally stable integration with reasonable representation of the molar concentration distribution of isotopie molecules in a rotating cylinder. The method includes a Gaussian elimination procedure which consists of the transformation of the Jacobian matrix to a triangular matrix followed by the backward elimination.

Computations are made on UF₆ gas in various centrifuges which have the openings for feed, product and waste on the end plates. Discussions are also presented on gas flows and separative efficiencies for the centrifuges which have baffle plates, skirting plates and bellows.