共查询到19条相似文献,搜索用时 203 毫秒
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共振参数计算是反应堆堆芯设计计算中的重要内容,传统的共振计算模型只适应于简单几何计算。本工作应用A.Hebert提出的子群共振自屏计算模型研制了复杂几何燃料组件的共振自屏计算程序。该程序能处理含有两种共振核素的复杂几何下的共振自屏。对一系列问题的数值校验计算表明,该模型在低富集度时具有较好的计算精度。 相似文献
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共振计算是反应堆组件堆芯设计和燃料管理的基础.子群共振计算方法基于共振能群子群截面,调用输运程序作为求解器,对子群中子注量率进行求解并且归并得到有效共振自屏截面,实现任意二维复杂几何的共振计算.由于子群方法在每个共振能群内部需要反复调用输运求解器,因此和等价理论相比速度较慢及本文基于子群方法的理论模型和自主开发的子群共振计算程序,提出并且完成了多群数据库、输运计算源项及多共振核素迭代的优化方案.通过基准题的验证可知,该方案在保持精度的同时提高了子群程序的计算效率,保证了该程序在工程上的实用性. 相似文献
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《核动力工程》2017,(5):18-23
为了适应材料几何布置越来越复杂的小型研究堆计算需求,基于构建实体几何理论和矩阵特征线方法,开发了具有复杂几何输运计算能力的2维特征线程序MOCAGE,并采用OpenMP并行编程模型对几何前处理中的特征线追踪进行并行化设计。通过不规则几何问题以及3种不同控制棒布置形式的HTTR基准题对程序的特征线追踪能力与计算精度进行评估,给出了计算结果与MCNP5多群计算参考值的相对误差。结果表明:所开发的程序能够正确实现对复杂对象的几何建模并进行特征线追踪,计算结果与参考值符合较好,精度满足程序验证要求,采用OpenMP并行编程能显著减少几何预处理时间。 相似文献
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特征线法是目前求解反应堆中子输运方程的主要计算方法之一。本文开发了基于OpenMP的中子输运方程特征线法并行计算程序,以提高特征线法的计算效率。OpenMP是共享存储体系结构上的一个并行编程模型,采用Fork-Join并行执行方式,适合于SMP共享内存多处理系统和多核处理器体系结构。通过相关基准题测试验证,表明所开发的程序在有效增殖因数以及相对中子通量(归一化栅元功率)分布等参数上都能取得良好的精度,且使用OpenMP能取得良好的加速效果,使计算时间显著减少。 相似文献
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Based on the combination of subgroup method and characteristics method, a resonance self-shielding calculation code SGMOC is programmed. SGMOC code can handle the complex (both in geometry and resonant components) resonance problems. The numerical results are in good agreement with those of MCNP. In order to improve the SGMOC calculation accuracy, two techniques are utilized, i.e., the resonance interference effects between resonant nuclides are considered, and on the other hand, the elastic scattering resonance is taken into account. These two techniques can enhance the accuracy remarkably. 相似文献
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传统的基于矩形和六角形几何的堆芯计算程序已不适用于具有复杂几何的新型反应堆堆芯计算,本文开展了基于任意三角形网格的多群中子扩散变分节块方法研究。首先,采用ANSYS软件对计算区域进行三角形网格剖分,并利用坐标变换将任意三角形变换为正三角形;其次,采用Galerkin变分技术建立包含节块中子平衡方程的泛函,将三角形节块内变量利用正三角形内正交基函数进行展开;最后,利用变分原理,获得中子通量密度与节块边界上分中子流的响应关系,并基于传统的源迭代法对其进行求解。基于上述理论模型开发了程序TriVNM,并采用不同几何基准题进行了验证。结果表明,TriVNM计算的堆芯keff和归一化功率分布与参考解吻合较好,该计算方法适用于复杂几何堆芯扩散计算。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(8):571-580
A new method for obtaining three-dimensional neutron flux distribution in a reactor has been developed by taking into account the fact that the X-Y planar geometry is generally complex but the geometry along Z-axis is simple. In this method, the finite element method is applied to the X-Y plane calculation and the finite difference method to the Z-axis. For solving a three-dimensional neutron diffusion equation, these two methods are iterated successively until a consistency of the leakage coefficients is attained between the two. The present method is embodied as a computer program FEDM for FACOM M200 computer. With this program, a three-dimensional diffusion calculation was performed for comparing some numerical results with those by a conventional standard computer code ADC. The comparison has shown that they agree well with each other. Computing time required for this problem by the FEDM was shorter than that by the ADC for obtaining same accuracy on the eigenvalue. To indicate usefulness of this method, a demonstration calculation for a reactor with a complex geometry was performed, which was a difficult case to calculate with a conventional finite difference code. 相似文献
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针对各种研究堆、实验堆以及新型反应堆中广泛应用的复杂几何燃料的共振计算难题,本文基于全局 局部耦合策略开展了可处理复杂几何燃料的等效几何共振计算方法研究。针对复杂几何燃料的孤立问题,基于燃料的逃脱概率守恒,建立了复杂几何燃料模型的等效一维圆柱(或平板)燃料模型;基于燃料到外围结构材料区的碰撞概率守恒,获得了燃料外围结构材料的等效尺寸;根据复杂几何燃料的丹可夫因子守恒,建立了等效一维圆柱(或平板)燃料外围的慢化剂尺寸;针对等效一维圆柱(或平板)燃料模型,采用伪核素子群方法进行了有效自屏截面计算。将该方法应用于非棒状几何燃料的共振计算,结果表明,该方法具有很强的几何处理能力,且具有较高的计算精度和计算效率。 相似文献
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The wavelets expansion method is widely used in various fields due to its powerful ability to simulate the oscillating functions. This method is applied to discretize the energy variable of neutron angular flux within the resonant energy range. Meanwhile, the conventional multi-group method is applied in fast and thermal energy ranges. This coupled method can obtain the problem-dependent continuous-energy neutron flux spectrum within the resonant energy range. The method of characteristics (MOC) is employed as a space-variable solver in this paper to keep the powerful capability of dealing with the complex geometry problems. A pressurized water reactor (PWR) fuel cell problem with UO2 fuel (UOX) and mixed oxide fuel (MOX), and a cylindrical cluster fuel problem are calculated by utilizing this coupled method. Results of these problems are all in good agreement with the results of the Monte Carlo statistical transport code MCNP. It is concluded that this is a valuable method to solve the resonance self-shielding calculation problems in a complex geometry, and it is promising to be applicable for realistic reactor problems. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(10):1182-1187
A simple and efficient method to estimate the Dancoff factor in a complicated geometry, named “the Neutron current method,” is presented in this paper. In this method, Dancoff factors are evaluated from the flux values obtained by the method of characteristics (MOC). By setting appropriate neutron sources in the non-fuel regions of target geometry and then executing fixed source calculation by MOC, the neutron current method can evaluate Dancoff factors for complicated geometry. It was demonstrated that the neutron current method can easily be adopted for complicated geometries, such as a PWR fuel assembly or large-scale geometry that is difficult to handle by the traditional collision probability method. By utilizing the neutron current method instead of a traditional collision probability method, the calculation time of Dancoff factors in complicated large geometry is drastically reduced. 相似文献
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基于NECP-X程序中已经研发的全局-局部耦合共振计算方法,研究了针对非棒状几何燃料的共振计算方法。首先,采用中子流方法计算真实问题的丹可夫修正因子,以处理全局的空间效应;其次,基于丹可夫修正因子等效获得小规模问题周围慢化剂的几何信息;最后,对于小规模问题燃料区的有效自屏截面的计算采用共振伪核素子群方法。将该方法应用于非棒状几何燃料数值计算,结果表明,该方法在处理非棒状几何燃料栅元的共振计算时,与蒙特卡罗结果程序相比,微观吸收截面偏差不超过1.8%,无限介质增殖因数偏差不超过110 pcm(1 pcm=10-5),具有较高的计算精度;在大规模问题的计算中,基于板状燃料的JRR-3M实验堆全堆在整个燃耗过程有效增殖因数偏差均在300pcm左右,组件功率偏差在整个燃耗过程不超过0.62%。因此,本研究提出的共振计算方法具有较高的正确率和精度。 相似文献