Computer Science ›› 2020, Vol. 47 ›› Issue (4): 30-35.doi: 10.11896/jsjkx.191100045

• Computer Architecture • Previous Articles     Next Articles

Application of Atomic Dynamics Monte Carlo Program MISA-KMC in Study of Irradiation Damage of Reactor Pressure Vessel Steel

WANG Dong1,2, SHANG Hong-hui2, ZHANG Yun-quan1,2, LI Kun2,3, HE Xin-fu4, JIA Li-xia4   

  1. 1 College of Information Engineering,Dalian Ocean University,Dalian,Liaoning 116023,China;
    2 State Key Laboratory of Computer Archintecture,Institute of Computing Technology,Chinese Academy of Sciences,Beijing 100190,China;
    3 School of Computer and Control Engineering,University of Chinese Academy of Sciences,Beijing 100190,China;
    4 China Institute of Atomic Energy,Beijing 102413,China
  • Received:2019-11-06 Online:2020-04-15 Published:2020-04-15
  • Contact: SHANG Hong-hui,born in 1984,Ph.D,associate professor.Her main research interests include the development of the first-principles methods and their applications on the high-performance computer systems.
  • About author:WANG Dong,born in 1995,postgra-duate.His main research interests include computer application technology and so on.
  • Supported by:
    This work was supported by the National Key Research and Development Program of China (2017YFB0202302)

Abstract: With the rapid development of material science,the microstructure of nuclear materials (reactor pressure vessel steel) is subject to radiation damage.The behavior of solute precipitation in reactor pressure vessel steel can be simulated by dynamic monte carlo method.In order to provide theoretical basis for studying the microstructure evolution and performance change of nuclear materials after long-term service,this paper introduced the parallel strategy and large-scale test results of MISA-KMC program developed by ourselves.Based on the correctness of the program,the precipitation process of solute atoms in reactor pressure vessel steel was studied by MISA-KMC program.The results show that,after a long period of evolution,solute atoms will aggregate to form Cu-rich clusters,which is one of the main microstructure leading to the embrittlement of steel in the reactor pressure vessel.The accuracy of the simulation results of MISA-KMC program,the size of the simulation that can be supported,and the diversity of simulation elements provide a guarantee for the subsequent research on material performance changes.

Key words: Irradiation embrittlement, Kinetic monte carlo, Solute precipitation, Thermal aging

CLC Number: 

  • TP311.52
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