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1.
特征线方法一般采用平源近似来求解,平源近似需要大量较小的网格才能获得精确的结果,从而会消耗较多内存,影响计算效率.相比平源近似,线性源可在网格较少的情况下得到较精确的数值结果.本文提出一种基于最小二乘的线性源特征线方法,并通过计算压水堆栅元及C5G7基准题等算例,对该方法进行了分析.数值结果表明,基于最小二乘的线性源特...  相似文献   

2.
汤春桃 《原子能科学技术》2011,45(12):1414-1420
基于非结构网格的中子输运方程特征线解法已成为堆芯设计程序中组件输运计算的标准方法之一。但现有的大部分特征线法程序均是基于平源近似的步特征线法模型开发的,平源近似是特征线法中除角度变量直接离散外又一基本假定。本工作提出一种基于线性源近似的中子输运方程特征线解法,并提出相关负中子源分布的修正方法。采用自行研制的数值计算软件PEACH,对OECD/NEAC5G7-MOX2D基准问题和自定义沸水堆小堆芯问题进行检验。数值计算结果表明,本工作提出的线性源近似特征线法模型在相同计算精度的前提下,占用更少的系统内存和运行时间。  相似文献   

3.
为探讨两维/一维综合法堆芯分析方法,本文基于特征线法研制了一维中子输运程序--PEACH-1D.不同于通常的平源近似特征线方法,PEACH-1D可对子区的中子源项作线性近似;程序运用指数函数插值表和渐近源外推技术来加速计算过程.相关数值结果表明,PEACH-1D具有很高的计算精度和效率,线性源近似的特征线法具备处理较粗网格的能力,值得推广.  相似文献   

4.
提出了一种在网格内部采用线性源分布的特征线方法,并且编写了线性源特征线方法程序TCM_L.数值计算结果表明,线性源特征线方法的计算精度高于平源特征线方法和简化线性特征线格式SLC;使用大网格计算的线性源特征线方法在保证计算精度的同时可以节省大量的存储空间和计算时间.  相似文献   

5.
离散纵标法是求解中子输运方程的主要数值方法之一,空间变量离散及误差控制对保证输运计算精度至关重要。传统有限差分离散方法对于特定模型会产生非物理振荡问题,粗网精度不足使得低阶差分方法的应用具有局限性。本文研究了二维常数和线性短特征线方法,短特征线空间离散基于中子输运的特征线解,根据输运方程的空间矩守恒构造网格角通量密度完成输运方程求解。选取固定源和临界问题进行测试验证并分析了网格敏感性。数值结果表明,线性短特征线离散对网格敏感性较低,较常数短特征线和低阶差分方法具有更高的计算精度及效率。  相似文献   

6.
基于Tikhonov正则化法,以单层、双层以及三层屏蔽的152Eu点源为例,对γ多层屏蔽材料厚度进行了反解研究。结果表明:Tikhonov正则化法能够给出比最小二乘法更稳定且可靠的计算结果。相对于线性吸收系数的计算与测量值的偏差,γ特征谱线的选取是影响反解结果的主要因素。  相似文献   

7.
基于三角形网格的穿透概率方法研究   总被引:1,自引:0,他引:1  
刘萍萍  吴宏春 《核动力工程》2006,27(5):12-18,41
研究了基于三角形网格的中子输运方程穿透概率方法.网格子区内部中子源采用平源分布,子区界面中子角注量密度空间分布设为均匀,角度分布采用简化4Pi近似,并采用一种按照非结构网格编码顺序进行网格扫描的新方法.编制了适应于二维任意形状几何中子输运特征值问题求解的程序TPTRI,对一些二维输运基准问题作了计算.与MG-MCNP3B、SURCU、TEPFEM等程序结果进行了比较分析,结果吻合很好.  相似文献   

8.
子群法与特征线法结合的中子共振计算   总被引:1,自引:1,他引:0  
黄世恩  王侃  姚栋 《原子能科学技术》2010,44(10):1201-1206
传统的中子共振自屏计算方法采用了有理近似,局限于处理简单的共振模型,在处理复杂燃料栅元/组件时会引入较大误差。为提高复杂情况下共振计算的精度,将子群法共振模型与特征线方法结合,推导了子群法-特征线法方程。基于WIMSD格式的69群数据库,编制了可用于任意二维几何中子共振计算的SGMOC程序。通过数值验证表明,该程序计算结果与MCNP程序计算结果吻合良好,具有较高的计算精度与几何通用性。  相似文献   

9.
不规则四边形网格中X射线能量沉积算法研究   总被引:1,自引:1,他引:0  
对X射线辐照圆柱壳体的平面应变热-力学效应进行数值模拟,需解决不规则四边形网格中的能量沉积计算问题。本文采用严格的积分方法对不规则四边形网格内的能量沉积进行了计算,得到了相对精确的能量沉积结果,同时还给出了3种简便算法,并将近似结果与精确解进行了对比。结果表明,中点积分法和平行四边形近似法既省时又具有高精度,能很好取代积分方法计算能量沉积,且中点积分法不受网格划分的限制,具有更好的普适性;余弦近似法虽更省时但误差较大,数值模拟中不宜采用。  相似文献   

10.
杨睿  胡赟  单浩栋  徐李 《原子能科学技术》2020,54(11):2145-2152
边界条件处理是特征线方法(MOC)向任意三维几何拓展时遇到的难点之一。本文提出一种边界条件处理方法,既保留循环特征线中首尾相连的特性,又能像插值方法一样适用于任意几何。首先推导了平源近似下的特征线方程,提出了一种将源项和边界角通量分离处理的内迭代解法。然后证明了该解法具有唯一解,并类似于循环特征线方法给出解的构造方法。最后借助数值积分和权重插值给出迭代计算流程。采用Takeda算例、单铀球水腔模型和C5G7算例进行验证计算,keff的最大计算误差分别为21、319和138.8 pcm,表明方法可靠。该方法可应用于任意几何,且不需存储边界通量和进行边界迭代。  相似文献   

11.
ABSTRACT

An efficient numerical scheme for time-dependent MOC calculations is proposed. In the present scheme, one of the most successful factorization method, the multigrid amplitude function (MAF) method, is employed to achieve faster computation with the minimum degradation for the temporal integration of the scalar flux. In addition, the MAF method is re-derived based on the linear source approximation, which is not applied for time-dependent MOC calculations in the past studies as far as the authors’ knowledge, to reduce the spatial discretization error with the coarser flux region separation. The accuracy and computational time of the present scheme are evaluated through the calculation of the TWIGL and the C5G7-TD 2D benchmark problems. The present calculation results show that the present scheme is 6.2 times faster than the conventional method while achieving the same accuracy in the C5G7-TD benchmark problem.  相似文献   

12.
Boundary condition processing is one of the difficulties encountered in the application of method of characteristics (MOC) to arbitrary three-dimensional geometry. In this paper, a boundary condition processing method was proposed, which not only preserved the track continuity as cyclic track method, but also could be applied to arbitrary geometry as the interpolation method. The MOC equation was derived under the flat source approximation and an internal iterative method was proposed in which the source term and the boundary angular flux were processed separately. It was proved that the equation had a unique solution which could be constructed similarly to the cyclic track method. The iterative calculation flow was given by numerical integration and weight interpolation. Takeda benchmark, single uranium sphere model with water cavity and C5G7 benchmark were calculated to test the accuracy. The maximum error of keff is 21, 319 and 138.8 pcm respectively, which shows that the method is reliable. This method can be applied to arbitrary geometry without storing boundary fluxes and performing boundary iteration.  相似文献   

13.
In this paper, the diamond-difference (DD) scheme, which is commonly used in discrete-ordinate codes, is applied to the method of characteristics (MOC) to reduce the spatial discretization error of the flat flux approximation. Smaller spatial discretization error allows coarser background mesh division, which leads to smaller computational burden. Some theoretical considerations on the DD scheme are discussed to clarify the strength of this method. An absorption cross section weighted DD scheme (AWDD), which utilizes macroscopic absorption cross section to set the weight, is also discussed. The DD and AWDD schemes are implemented to AEGIS, which is a lattice physics code based on MOC. Then the AEGIS code is applied to two different benchmark problems whose spatial discretization errors are large. The calculation results indicate that from the viewpoint of spatial discretization error, the AWDD scheme is superior to the conventional MOC in which the step characteristics approximation is commonly used. Since incorporation of the AWDD scheme to current MOC codes is very simple, it will be a good candidate of spatial discretization method for MOC codes.  相似文献   

14.
In this paper, we report the development and verification of a method of characteristics (MOC) code, PEACH, at Shanghai Jiao Tong University. Both the usual flat-source step characteristics (SC) scheme and the linear source (LS) approximation scheme are adopted for the tracking calculation along the neutron trajectory. The assembly-based modular ray tracing (AMRT) technique that possesses a good geometric flexibility and high efficiency is employed, which makes PEACH able to deal with practical LWR assembly and core problems. Moreover, in order to reduce the computational time of the MOC iteration process, both the multi/few-group two-level cell-based coarse mesh finite difference (CMFD) acceleration and the exponential function interpolation technique are used. This results in a significant acceleration. Numerical results for the OECD NEA C5G7 MOX benchmark problem and a 69-group BWR mini-core problem demonstrate that PEACH is accurate and efficient. Numerical results also demonstrate that the LS scheme is more efficient than the SC scheme, taking less time and system memory to generate results of comparable accuracy. In addition, we find that MOC with CMFD acceleration always converges with almost the same number of outer iterations regardless of the physical problem size and the discretization parameters used. This shows an ideal linear relationship between the run time and the geometric size of the problem.  相似文献   

15.
The transport cross-section based on inflow transport approximation can significantly improve the accuracy of light water reactor (LWR) analysis,especially for the treatment of the anisotropic scattering effect.The previous inflow transport approximation is based on the moderator cross-section and normalized fission source,which is approximated using transport theory.Although the accuracy of reactivity is increased,the P0 flux moment has a large error in the Monte Carlo code.In this s...  相似文献   

16.
For the method of characteristic (MOC), a system with large-gradient neutron flux caused by a strong absorber or neutron leakage is reported to entail large errors in spatial mesh discretization and require very fine mesh spacing. To apply the MOC to such fine models, the ray-trace path width has to be fine in order to make many paths cross each region. Our new method intends to obtain good accuracy with a coarse path width. With a coarse path width on the MOC, some tiny regions have less ray-tracing paths. The reliability of flux calculation for the regions can be evaluated with the calculation volumes that are estimated in ray tracing. If the discrepancy between the calculation and true volumes becomes large, the accuracy cannot be expected. In this study, the discrepancies were numerically evaluated, and it is found that the discrepancies occur on a very tiny region. To make the flux calculation of such tiny regions more reliable, an approximation, in which the outgoing flux is equal to the incoming neutron, is applied instead of the usual MOC equation. The criteria switching on the approximation, which is called filtering, was numerically evaluated for PWR assemblies. The method is validated with numerical benchmark calculations.  相似文献   

17.
基于各向同性散射的中子输运方程特征线方法,计算实际组件能谱时经输运修正后,散射矩阵中P0自散射截面可能出现一定量的负值,影响数值稳定性。本文开发了P1各向异性散射特征线方法,并研制了计算程序PEACH-A。压水堆栅元基准问题的验证结果表明,PEACH-A程序具有较高的计算精度。对典型富集度的UO_2、MOX燃料栅元及其组合问题进行了敏感性分析,结果表明,针对MOX燃料及富集度差异较大的UO_2燃料栅元组合问题有必要采用P1各向异性散射。  相似文献   

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