NUMA-Aware Data Management for Neutron Cross Section Data in Continuous Energy Monte Carlo Neutron Transport Simulation
- 1. Argonne National Laboratory 9700 S. Cass Avenue, Lemont, IL (United States)
Description
The calculation of macroscopic neutron cross-sections is a fundamental part of the continuous-energy Monte Carlo (MC) neutron transport algorithm. MC simulations of full nuclear reactor cores are computationally expensive, making high-accuracy simulations impractical for most routine reactor analysis tasks because of their long time to solution. Thus, preparation of MC simulation algorithms for next generation supercomputers is extremely important as improvements in computational performance and efficiency will directly translate into improvements in achievable simulation accuracy. Due to the stochastic nature of the MC algorithm, cross-section data tables are accessed in a highly randomized manner, resulting in frequent cache misses and latency-bound memory accesses. Furthermore, contemporary and next generation non-uniform memory access (NUMA) computer architectures, featuring very high latencies and less cache space per core, will exacerbate this behaviour. The absence of a topology-aware allocation strategy in existing high-performance computing (HPC) programming models is a major source of performance problems in NUMA systems. Thus, to improve performance of the MC simulation algorithm, we propose a topology-aware data allocation strategies that allow full control over the location of data structures within a memory hierarchy. A new memory management library, known as AML, has recently been created to facilitate this mapping. To evaluate the usefulness of AML in the context of MC reactor simulations, we have converted two existing MC transport cross-section lookup "proxy-applications" (XSBench and RSBench) to utilize the AML allocation library. In this study, we use these proxy-applications to test several continuous-energy cross-section data lookup strategies (the nuclide grid, unionized grid, logarithmic hash grid, and multipole methods) with a number of AML allocation schemes on a variety of node architectures. We find that the AML library speeds up cross-section lookup performance up to 2x on current generation hardware (e.g., a dual-socket Skylake-based NUMA system) as compared with naive allocation. These exciting results also show a path forward for efficient performance on next-generation exascale supercomputer designs that feature even more complex NUMA memory hierarchies.
Availability note (English)
Available from https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_04020.pdf; https://doaj.org/article/014b679207d54ce9981cbde25b648976Additional details
Identifiers
Publishing Information
- Journal Title
- EPJ. Web of Conferences
- Journal Volume
- 247
- Journal Page Range
- vp.
- ISSN
- 2100-014X
Conference
- Title
- International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
- Acronym
- PHYSOR2020
- Dates
- 28 Mar - 2 Apr 2020
- Place
- Cambridge (United Kingdom)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 53087719
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; COMPUTER ARCHITECTURE; COMPUTERIZED SIMULATION; CROSS SECTIONS; MEMORY MANAGEMENT; MONTE CARLO METHOD; NEUTRON TRANSPORT; NEUTRONS; PERFORMANCE; PROGRAMMING; REACTOR CORES; STOCHASTIC PROCESSES; SUPERCOMPUTERS; TOPOLOGY
- Descriptors DEC
- BARYONS; CALCULATION METHODS; COMPUTERS; DATA PROCESSING; DIGITAL COMPUTERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; MATHEMATICAL LOGIC; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; PROCESSING; RADIATION TRANSPORT; REACTOR COMPONENTS; SIMULATION