Preliminary study on CAD-based method of characteristics for neutron transport calculation

Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics (MOC). It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calculation. In our study, the diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the flat flux approximation. Based on MCAM and MOC, a new 2D MOC code was developed and integrated into the SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.     

Chapman-Enskog-maximum entropy method on time-dependent neutron transport equation

The time-dependent neutron transport equation in semi and infinite medium with linear anisotropic and Rayleigh scattering is proposed. The problem is solved by means of the flux-limited, Chapman-Enskog-maximum entropy for obtaining the solution of the time-dependent neutron transport. The solution gives the neutron distribution density function which is used to compute numerically the radiant energy density E(x,t), net flux F(x,t) and reflectivity R_f. The behaviour of the approximate flux-limited maximum entropy neutron density function are compared with those found by other theories. Numerical calculations for the radiant energy, net flux and reflectivity of the proposed medium are calculated at different time and space.     

先进中子学栅格程序KYLIN-2的开发与初步验证

针对先进核反应堆中结构复杂的燃料组件,中国核动力研究设计院开发了先进中子学栅格中子学程序KYLIN-2,该程序采用子群方法进行共振处理,采用特征线方法（MOC）进行复杂几何中子输运计算,并利用采用广义粗网格有限差分加速方法（GCMFD）来加速中子输运求解流程,采用基于改进预估校正临界-燃耗迭代方法（PPC）的切比雪夫方法求解复杂燃耗链,同时,为了方便用户使用,开发形成了支持复杂组件图形化建模工具和后处理显示工具。通过初步的数值检验,针对典型压水堆燃料组件,KYLIN-2具有较高的计算精度,满足工程使用需求。     

一种中子脉冲序列核信号高速相关函数计算方法

为解决基于PC机平台、高达1 GHz采样率下的相关函数计算的实时性需求,针对中子脉冲序列核信号本身所具有的结构特点,设计了高速、实时的相关函数计算方法,实现了采样率为1 GHz的中子脉冲序列核信号的实时相关函数计算。性能测试结果表明,算法达到了对中子脉冲序列核信号进行相关计算的时间在1 h以内的实时性要求,使得铀部件质量丰度的实时检测成为可能。     

中子脉冲序列核信号相关和功率谱实时计算

为解决基于PC机平台、高达1 GHz采样率下之相关计算和频谱分析对实时性要求的关键技术问题,针对中子脉冲序列核信号本身所具有的特殊的“0,1”结构特点,采用快速移动的方法,借助于内存管理及SSE优化设计,创建了优化频谱分析的流程,构造了高速、实时的相关计算和功率谱分析算法,实现了1 GHz采样率下的中子脉冲序列核信号的实时相关计算和频谱分析。性能测试结果表明,在计数率为3×106 s-1,单个块（长度为1 024）时,研究的相关算法的计算时间为0.29 μs,相应的英特尔数学内核库的相关计算时间为129.95 μs。现场实际试验表明,该算法达到了对中子脉冲序列核信号进行相关计算和频谱分析的实时性要求。     

新型热中子敏感微通道板探测效率的蒙特-卡罗模拟研究

基于microchannel plates (MCP)的中子探测技术近年来发展迅速, 因其具有较高的空间分辨率和中子探测效率以及优异的时间分辨能力, 可用于高分辨率中子照相和能量选择中子成像. 本文利用蒙特-卡罗(MC)程序, 对栅格为15 μm的热中子敏感MCP板进行MC模拟计算, 获得了不同几何结构和材料组成情况下, 掺杂型和镀膜型热中子敏感MCP板的探测效率. 计算结果表明, 增加中子敏感材料的比例可以获得更高的中子阻挡效率, 但同时也加大了次级粒子发射进入MCP板通道的难度, 掺杂型MCP 板的通道直径和镀膜型MCP板的镀膜厚度均存在最优值. MCP板厚度为0.4 mm时, 对¹⁰B₂O₃材料, 掺杂型MCP板的热中子探测效率可以超过40%, 镀膜型MCP板的热中子探测效率可以接近60%.     

Preliminary shielding analysis in support of the CSNS target station shutter neutron beam stop design

The construction of China Spallation Neutron Source (CSNS) has been initiated in Dongguan, Guangdong, China. Thus a detailed radiation transport analysis of the shutter neutron beam stop is of vital importance. The analyses are performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method. The target of calculations is to optimize the neutron beamline shielding design to guarantee personal safety and minimize cost. Successful elimination of the primary ray effects via the two-dimensional uncollided flux and the first collision source methodology is also illustrated. Two-dimensional dose distribution is calculated. The dose at the end of the neutron beam line is less than 2.5 μSv/h. The models have ensured that the doses received by the hall staff members are below the standard limit required.     

中子发生器束流传输光学系统研究及模拟计算

束流传输系统是中子发生器研制、调试和技改等工作顺利进行的重要依据。为此开展了中子发生器束流传输系统研究工作,阐述了传输系统光学特性和组成。以ns-200中子发生器为代表实例,详尽地分析了传输系统的组成和各光学透镜的特性。根据LEADS软件要求,生成该器束流传输系统数据输入卡,调用软件相应各光学元件计算模块,进行了模拟计算,给出了束流传输包络图。束流传输模拟计算结果与原设计要求基本一致。     

Microscopic calculation of the magnetic field of neutron stars

Based on the Dirac equation describing an electron moving in a uniform and cylindrically symmetric magnetic field which may be the result of the self-consistent mean field of the electrons themselves in a neutron star, we have obtained the eigen solutions and the orbital magnetic moments of electrons in which each eigen orbital can be calculated. From the eigen energy spectrum we find that the lowest energy level is the highly degenerate orbitals with the quantum numbers pZ=0, n=0, and m≥0. At the ground state, the electrons fill the lowest eigen states to form many Landau magnetic cells and each cell is a circular disk with the radius λfree and the thickness λe, where λfree is the electron mean free path determined by Coulomb cross section and electron density and λe is the electron Compton wavelength. The magnetic moment of each cell and the number of cells in the neutron star are calculated, from which the total magnetic moment and magnetic field of the neutron star can be calculated. The results are compared with the observational data and the agreement is reasonable.     

用多群蒙特卡罗方法计算快中子核临界keff和通量密度

用多群蒙特卡罗方法对快中子核裂变系统进行了临界计算。有效增殖因子keff的计算值与实验结果符合。计算所得中子通量密度的空间分布在球形裂变系统中随半径增大单调下降。中子通量密度的能量分布在由高浓缩铀组成的活性区内呈单一能量极大值,其对应能量对于裸球核裂变系统和具有反射层裂变系统分别为0.35MeV和0.25MeV,而在由天然铀组成的反射层中在0.1MeV附近出现能量双峰。由通量密度所得中子能谱在无反射层球形裂变系统中随半径增加变硬,在有反射层球形裂变系统中随半径增加变软。     

Microscopic calculation of the magnetic field of neutron stars

Based on the Dirac equation describing an electron moving in a uniform and cylindrically symmetric magnetic field which may be the result of the self-consistent mean field of the electrons themselves in a neutron star, we have obtained the eigen solutions and the orbital magnetic moments of electrons in which each eigen orbital can be calculated. From the eigen energy spectrum we find that the lowest energy level is the highly degenerate orbitals with the quantum numbers pz = 0, n = 0, and m ≥0. At the ground state, the electrons fill the lowest eigen states to form many Landau magnetic cells and each cell is a circular disk with the radius λfree and the thickness λe, where λfree is the electron mean free path determined by Coulomb cross section and electron density and λe is the electron Compton wavelength. The magnetic moment of each cell and the number of cells in the neutron star are calculated, from which the total magnetic moment and magnetic field of the neutron star can be calculated. The results are compared with the observational data and the agreement is reasonable.     

改进的线性子链方法在中子活化计算中的应用

在传统线性子链方法（TTA）采用的Bateman表达式基础上,利用极限运算推导出允许重复特征值出现的广义解析表达式,克服了重复核素对线性子链方法计算稳定性的限制,并通过回溯算法的应用实现了对核反应链的自动搜索。通过以上对线性子链方法的改进,显著提高了计算效率,最终形成了用于中子活化计算的程序ITACT。基于ITACT程序和EAF-2007数据库,计算了压水堆燃料包壳材料和聚变堆第一壁材料活化等例题,并将计算结果与欧洲活化程序FISPACT进行对比。结果表明：对于长寿命核素,两者的计算结果较为接近,对于短寿命核素,ITACT程序的计算精度更高,初步验证了ITACT程序的可用性和准确性。     

高效偶阶离散纵标法研究及初步验证

采用TAKEDA基准题验证高效偶阶离散纵标法(HEPSN)的临界计算功能,数值结果表明：有效增殖因数和各区域平均中子通量密度值与基准值吻合良好,堆芯区域的平均中子通量密度误差在0.7%以内,其他区域较扩散理论误差显著减小。相较于传统离散纵标法,HEPSN计算效率更高,需要的存储更小;相较于扩散理论,HEPSN的计算精度更高。因而,高效偶阶离散纵标法在大规模输运计算中具有很好的应用前景。     

聚变中子能谱测量系统脉冲中子灵敏度的实验研究

为多种复杂环境下的稳态和脉冲DT聚变中子能谱测量建立了一种灵敏度优化反冲质子磁谱仪. 使用成像板和同位素α源测量了谱仪的反冲质子能量-位置投影关系. 利用稳态加速器中子源平台、通过单粒子计数方法结合三维带电粒子输运程序模拟,研究了谱仪脉冲中子灵敏度能量响应. 通过高探测效率参数设置使谱仪对DT中子的探测效率达到2×10^-5 cm²水平,从而在较弱中子源上获得了较高统计精度实验数据. 程序模拟结果与谱仪α粒子刻度和DT中子标定实验结果取得了良好的一致性,可由此发展精细解谱技术,以提高脉冲中子能谱测量的灵敏度和能量分辨. 关键词： 聚变中子能谱 磁反冲质子 脉冲中子灵敏度 粒子输运     

用多群蒙特卡罗方法计算快中子核临界K_(eff)和通量密度

用多群蒙特卡罗方法对快中子核裂变系统进行了临界计算。有效增殖因子κｅｆｆ的计算值与实验结果符合。计算所得中子通量密度的空间分布在球形裂变系统中随半径增大单调下降。中子通量密度的能量分布在由高浓缩铀组成的活性区内里单一能量极大值,其对应能量对于裸球核裂变系统和具有反射层裂变系统分别为０．３５ＭｅＶ和０．２５ＭｅＶ,而在由天然铀组成的反射层中在０．１ＭｅＶ附近出现能量双峰。由通量密度所得中子能谱在无反射层球形裂变系统中随半径增加变硬,在有反射层球形裂变系统中随半径增加变软。     

球几何中子输运保正线性间断有限元格式

针对球几何中子输运方程线性间断有限元方法计算的负中子通量问题,构造了保正线性间断有限元格式,该格式保持中子角通量0阶矩和1阶矩。现有方法计算中子角通量非负时,采用传统的线性间断有限元方法,求解线性方程组;原方法计算出现负通量,则采用构造的保正格式,求解非线性方程组。编制了球几何中子输运问题保正格式程序模块,并集成到应用程序。数值算例表明构造的保正格式计算的中子通量非负,有效降低数值误差,提高数值计算的精度。     

JFNK在高温堆扩散计算中的应用

研究了JFNK框架下高温堆中子扩散问题的求解方法。研究结果表明,JFNK方法在求解与源迭代相同形式中子扩散方程时,相对残差下降趋势为逐渐加快并趋于稳定,有利于更高求解精度的实现。使用通量归一化附加方程可以获得更好的JFNK非线性迭代特性,但在算例中其部分牛顿修正方程求解时间偏多,总计算时间高于显式有效增殖系数附加方程法,需要研究更高效的JFNK预处理方法对线性求解环节进行改善。     

惰性气体输运性质的理论计算

利用惰性气体原子间相互作用势,系统计算了5种惰性气体的输运系数,包括第二维里系数B、扩散系数D、热传导系数λ、黏滞系数η和热扩散因子αT的计算.从输运性质的计算证明了TangToennies势模型的准确性. 关键词： 惰性气体 TangToennies势模型 输运系数 计算     

D-T中子与平板型聚乙烯材料作用的次级中子角度谱实验研究

基于反冲质子法建立了一种测量D-T中子与平板型宏观样品作用的次级中子角度谱的实验方法.为保证探测器的能量线性并在较低的中子有效测量下阈(0.5 MeV)情况下获得好的中子-伽马射线甄别性能,采用高、低能段分别测量的方法.采用事件记录法,同时记录了次级中子和伴随伽马射线的脉冲形状甄别和脉冲幅度二维信息,利用基于ROOT数据分析平台编写的离线数据分析程序,完成了伴随伽马射线的挑选和扣除,以及高、低两能段反冲质子谱的拼接,并成功的将神经网络技术应用于中子能谱的解谱,获得了D-T中子与9和18 cm厚平板型聚乙烯材料作用的0.5-15 MeV的次级中子角度谱实验结果.实验模型的MC模拟由MCNP5完成,数据库采用ENDF-VI,实验结果和MC计算结果在实验不确定度范围内一致. 关键词： D-T中子 积分中子学 反冲质子法 次级中子能谱     

三维中子-光子输运的蒙特卡罗程序MCMG

三维中子-光子输运蒙特卡罗程序MCMG发展了针对物质的碰撞机制,几何块、几何面动态可扩展, 随机数周期进一步扩大到261。可进行多群-连续截面耦合计算,多群散射展开到P5,并考虑了中子上散射,程序配备了通用和专用多群截面库。MCMG模拟取得了与MCNP程序和实验一致的结果,串行计算速度较MCNP快2~4倍,可进行上万处理器核的并行计算。