共查询到17条相似文献,搜索用时 62 毫秒
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随着科学研究的不断深入、计算条件和对设计计算精度要求的不断提高,全堆芯Pin-by-pin计算已成为了下一代堆芯数值计算方法研究热点。超级均匀化方法作为全堆芯Pin-by-pin计算的均匀化方法主流方法之一被广泛使用。针对燃料组件采用传统超级均匀化方法,对存在中子泄漏的反射层组件采用空间泄漏相关的超级均匀化方法,产生了包含超级均匀化因子在内的等效均匀化常数。基于三维C5G7基准题,分析了此等效均匀化常数计算方式在非均匀性较强、中子泄漏较大反应堆堆芯的中子学计算精度。数值结果表明:与传统组件均匀化计算方法相比,应用了超级均匀化方法的堆芯Pin-by-pin计算的计算精度更高。 相似文献
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基于指数函数展开节块3阶简化球谐函数(EFEN-SP3)方法,通过采用基于标准消息传递界面(MPI)的空间并行算法实现高性能全堆芯Pin-by-pin计算,并开发了相应的程序EFEN。该程序通过合理设计区域划分方案以保证负载平衡并使通信次数最小化,充分发挥并行中央处理器(CPU)的计算和存储能力;通过选择红黑Gauss-Seidel节块扫描算法避免区域分解引起的迭代格式退化。参考实际商用堆的堆芯布置,设计2个压水堆(PWR)全堆芯Pin-by-pin算例,相应的数值结果表明:该程序计算结果的精度在可接受范围内;通信周期对计算精度和并行效率的影响都很小;子区域表面体积比较小的区域划分方式具有较高的并行效率;用125个CPU进行一次空间网格数为289×289×218、能群数为4的PWR全堆芯Pin-by-pin计算所需时间约为900 s,并行效率约为90%。 相似文献
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堆芯中子学计算是反应堆设计分析的基础,为提高堆芯中子学计算的模拟分辨率与计算精度,开发了反应堆堆芯先进中子学模拟软件(SCAP-N)。该程序首先根据轴向特征对堆芯进行分层,并逐层进行二维堆芯非均匀输运计算,再采用超级均匀化方法(SPH)获得栅元等效均匀化截面,最后进行三维堆芯逐棒(pin-by-pin)输运计算,获得堆芯有效增殖因子与精细棒功率分布。为提高程序计算效率,采用分布式/共享式(MPI/OPENMP)混合并行方式对程序进行了并行化开发。利用虚拟反应堆(VERA)系列基准例题及美国先进非能动压水堆(AP1000)启动物理试验实测数据对程序进行了测试验证。结果表明,相比于商用核设计程序系统,SCAP-N程序采用的逐棒输运技术能够提高堆芯中子学的计算精度。与同类型高精度中子学程序相比,SCAP-N具有更高的计算效率,可进一步提高核电厂的经济性及运行灵活性。 相似文献
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球床氟盐冷却高温堆的控制棒位于侧反应射层内,存在无裂变中子源且受堆芯泄漏谱强烈影响的强吸收体区域扩散计算难题。超级均匀化方法(Super Homogenization,SPH)被用于对氟盐球冷却床堆侧反射层中控制棒区域的强吸收体进行等效均匀化处理,同时堆芯除控制棒区域外采用谱修正方法(Spectra Modification,SM),将输运计算的结果作为基准进行验算。结果表明,SM-SPH模型能有效地计算球床氟盐冷却高温堆反射层控制棒价值及通量分布,并且较常规的SPH方法能更好地处理棒间干涉效应。 相似文献
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Super homogenization (SPH) method was used as the homogenization technique of PWR core Pin-by-pin calculation. For the fuel assembly, the traditional SPH method was used to generate the group constants. For the reflector-assembly, the spatial leakage dependent SPH method was evaluated. The problem of non-convergence in the iteration of SPH factors calculation was solved by improved SPH method which can keep the neutron leakage and reaction activity conserved. Based on KAIST benchmark, the performance of the SPH method applied in PWR core Pin-by-pin calculation was evaluated. Numerical results demonstrate that compared with the results of traditional assembly-homogenized calculation, the Pin-by-pin calculations have the higher accuracy. 相似文献
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传统的栅元等效均匀化计算方法一般采用体积-通量权重法,保证了在反射边界条件下各群通量和反应率的守恒,但该方法在边界入射流较强时有一定误差。本文提出了一种改进的等效均匀化方法,该方法以栅元边界入射流与出射流之间的响应等效作为理论基础,认为不需要保证等效前后的平均通量守恒,而应保证入射流与出射流以及各群反应率之间的响应关系守恒。和原有均匀化方法相比,改进方法几乎不增加任何计算量。对带反射层的平板问题及C5G7MOX基准例题分别进行测试计算,结果表明,改进的栅元等效均匀化方法对特征值和棒功率分布的计算精度有明显的改善作用。 相似文献
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压水堆燃料组件输运燃耗耦合计算通常采用的是传统的预估-校正(PC)燃耗方法。然而,该方法本身的假设导致其存在一定的计算误差。为进一步提高燃耗计算的精度,本文针对传统的预估-校正燃耗方法的缺陷研究了改进的预估-校正燃耗方法,改进了对核反应率进行修正的高阶预估-校正燃耗方法,并在Bamboo-Lattice程序中进行了程序实现,对该方法进行了验证分析。结果表明:改进的预估-校正燃耗方法和高阶预估-校正燃耗方法在保证计算效率的前提下提高了燃耗计算的精度。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(6):376-387
A parallel production code, SCOPE2, has been developed for advanced calculations in the reactor core design of PWRs. In SCOPE2, the multi-group diffusion and/or SP3 transport equations are solved by the Red/Black iterative method within the framework of the finite difference method or the advanced nodal method without non-linear iterations. The effects due to pin-cell homogenization are taken into account by using the SPH factors. In this paper, calculation methods needed for fast computation are derived including efficient response matrix formulation of the nodal-SP3 method, an analytic solution of the flux moments in the nodal-SP3 transport equations, and coarse-group coarse-mesh diffusion acceleration method. It was found that the present pin-by-pin nodal-SP3 method was more accurate than the finite difference SP3 method with a small additional computational cost in the same meshing scheme. Tracking calculations of a commercial PWR plant by SCOPE2 revealed that the present model accurately predicted the power distribution and critical boron concentration. A set of depletion calculations in a typical design scheme can be completed within a few hours running on a PC-cluster (16 processors) for the full-core geometry of a 3-loop PWR with 340×3407times;26 meshes based on the 9-group pin-by-pin nodal-SP3 method. 相似文献
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计算效率是制约pin-by-pin计算工程应用的主要因素之一。本文利用三维扩散的非均匀变分节块法的非均匀节块的描述能力,在不改变原问题栅元均匀化材料分布的前提下,将传统pin-by-pin计算中使用的均匀材料细网剖分方式替代为非均匀材料粗网剖分方式(粗网加速方法),既能保证pin-by-pin的计算分辨率,又能显著降低红 黑迭代所需的浮点数操作数目,减小内迭代的计算代价。针对外迭代,运用广义矩阵分离加速(GPM)算法和粗网有限差分(CMFD)算法提高源迭代的收敛速度,降低计算时间。数值结果表明,提出的加速算法能在保证计算精度的前提下,有效提高pin-by-pin计算的效率。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(11):1143-1150
A cell calculation method has been developed for accurately treating neutron transport and heterogeneity effects of control rods (CRs) within the bounds of homogeneous neutron diffusion theory. In this method, CR cell-averaged homogeneous neutron cross sections are calculated by a heterogeneous neutron transport calculation with an annular supercell model, in which a CR assembly is surrounded by a homogeneous fuel region. Then, a neutron diffusion calculation is carried out using the homogeneous neutron cross sections in the same supercell, and the CR cell-averaged radial neutron diffusion coefficients are modified in an iterative manner such that the CR cell-interface neutron current which is obtained by the heterogeneous transport calculation can be reproduced by the homogeneous diffusion calculation. In the case of a 1,000-MWeclass FBR, the center CR worth, which was calculated by an RZ diffusion calculation using the cross sections obtained by the above method, agreed within 1% with that obtained by a heterogeneous transport calculation, proving the validity of the method. 相似文献
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以美国H.B.Robinson-2#机组反应堆压力容器(RPV)基准实验的参数为输入数据,采用三维离散纵标方法程序(TORT)计算压力辐照监督管处中子能谱及典型核素的活度值。计算得到的辐照监督管处中子能谱与基准实验结果趋势一致、吻合较好;典型核素活度的计算值与测量值之比(C/M)为1.04±0.04。用TORT对福建宁德核电站堆内构件释热率分布进行初步计算,并与蒙特卡罗方法(MCNP)的计算结果相比较,两种方法的结果表现出良好的一致性。最后对TORT程序应用于堆内释热率计算进行讨论。 相似文献