• 中国计算机学会会刊
  • 中国科技核心期刊
  • 中文核心期刊

Computer Engineering & Science ›› 2021, Vol. 43 ›› Issue (04): 681-688.

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Porting of reactor core programs in ARM environment

MING Ping-zhou1,LI Zhi-gang1,LIU Ting1,LU Wei2,LIU Dong1,ZENG Hui1,YU Hong-xing2#br# #br# #br#   

  1. (1.Nuclear Power Institute of China,Chengdu 610213;

    2.Science and Technology on Reactor System Design Technology Laboratory,

    Nuclear Power Institute of China,Chengdu 610213,China)
  • Received:2020-04-28 Revised:2020-06-09 Accepted:2021-04-25 Online:2021-04-25 Published:2021-04-21

Abstract: In order to demonstrate the feasibility of domestic chips in the field of reactor core calculation, some reactor core programs are ported in the ARM computing environment of Phytium processor, involving the diffusion prototype program NACK-R of the core fuel management software, and sub-channel analysis program CORTH, characteristic line transport program OpenMOC, and core assembly program KYLIN2. Through reasonable program code revision, the dependence on commercial function libraries are removed, and the OpenMP parallelism is introduced in the trace process of MOC in the ARM environment so that the parallel ability of multiple Phytium processor cores in one cluster node can be investigated. The frequency of the reference Intel commercial processor is about twice that of the Phytium processor, and the difference between the serial running efficiency of the ported programs are kept at 3~4 times. Due to the cache size of the Phytium processor, the performance difference of some large input data cases may be greater. After OpenMP parallelism, the running efficiency of KYLIN2 is close to the serial efficiency of Intel computing environment, which proves that the single node with multiple Phytium processors can replace some schemes of nuclear engineering calculation. The program porting results also show that the hybrid cluster system with different types of processors can fully utilize domestic hardware in the case of computing resource crisis and improve the overall utilization.





Key words: reactor core calculation, nodal method, sub-channel method, characteristic line transport method, ARM64, program porting, OpenMP