Enabling high-fidelity neutron transport simulations on petascale architectures

D. Kaushik, Micheal Smith, A. Wollaber, Barry F. Smith, A. Siegel, W. Yang
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引用次数: 26

Abstract

The UNIC code is being developed as part of the DOE's Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. UNIC is an unstructured, deterministic neutron transport code that allows a highly detailed description of a nuclear reactor. The primary goal of our simulation efforts is to reduce the uncertainties and biases in reactor design calculations by progressively replacing existing multilevel averaging (homogenization) techniques with more direct solution methods based on first principles. Since the neutron transport equation is seven dimensional (three in space, two in angle, one in energy, and one in time), these simulations are among the most memory and computationally intensive in all of computational science. In order to model the complex physics of a reactor core, billions of spatial elements, hundreds of angles, and thousands of energy groups are necessary, leading to problem sizes with petascale degrees of freedom. Therefore, these calculations exhaust memory resources on current and even next-generation architectures. In this paper, we present UNIC simulation results for two important representative problems in reactor design and analysis---PHENIX and ZPR-6. In each case, UNIC shows good weak scalability on up to 163,840 cores of Blue Gene/P (Argonne) and 122,800 cores of XT5 (Oak Ridge). While our current per processor performance is less than ideal, we demonstrate a clear ability to effectively utilize the leadership computing platforms. Over the coming months, we aim to improve the per processor performance while maintaining the high parallel efficiency by employing better algorithms such as spatial p- and h-multigrid preconditioners, optimized matrix-tensor operations, and weighted partitioning for better load balancing. Combining these additional algorithmic improvements with the availability of larger parallel machines should allow us to realize our long-term goal of explicit geometry coupled multiphysics reactor simulations. In the long run, these high-fidelity simulations will be able to replace expensive mockup experiments and reduce the uncertainty in crucial reactor design and operational parameters.
在千万亿级架构上实现高保真中子输运模拟
UNIC代码是美国能源部核能高级建模与仿真(NEAMS)项目的一部分。UNIC是一种非结构化的、确定性的中子传输代码,允许对核反应堆进行非常详细的描述。我们的模拟工作的主要目标是通过逐步用基于第一性原理的更直接的解决方法取代现有的多层平均(均质)技术来减少反应堆设计计算中的不确定性和偏差。由于中子输运方程是七维的(三个空间,两个角度,一个能量,一个时间),这些模拟是所有计算科学中内存和计算强度最大的。为了模拟反应堆堆芯的复杂物理,需要数十亿个空间元素、数百个角度和数千个能量组,从而导致具有千万亿级自由度的问题规模。因此,这些计算耗尽了当前甚至下一代架构的内存资源。在本文中,我们给出了在反应堆设计和分析中两个重要的代表性问题——PHENIX和ZPR-6的UNIC模拟结果。在每种情况下,UNIC在Blue Gene/P (Argonne)的163,840核和XT5 (Oak Ridge)的122,800核上都显示出良好的弱可扩展性。虽然我们目前的每处理器性能不太理想,但我们展示了有效利用领先计算平台的清晰能力。在接下来的几个月里,我们的目标是提高每个处理器的性能,同时通过采用更好的算法,如空间p-和h-多网格预处理,优化矩阵张量操作和加权分区来保持高并行效率,以实现更好的负载平衡。将这些额外的算法改进与更大的并行机器的可用性相结合,应该使我们能够实现显式几何耦合多物理场反应堆模拟的长期目标。从长远来看,这些高保真模拟将能够取代昂贵的模拟实验,并减少关键反应堆设计和操作参数的不确定性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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