Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2018 Impact factor 0.961

Nuclear Science and Techniques ›› 2018, Vol. 29 ›› Issue (9): 124 doi: 10.1007/s41365-018-0471-4

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Development and validation of the code COUPLE3.0 for the coupled analysis of neutron transport and burnup in ADS

Lu Zhang 1,2 • Yong-Wei Yang 1 • Yuan-Guang Fu 3,4 • De-Liang Fan 1 • Yu-Cui Gao 1   

  1. 1 Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
    2 University of Chinese Academy of Sciences, Beijing 100049, China
    3 Institute of Applied Physics and Computed Mathematics, Beijing 100088, China
    4 CAEP Software Center for High Performance Numerical Simulation, Beijing 100088, China
  • Contact: Yong-Wei Yang E-mail:yangyongwei@impcas.ac.cn
  • Supported by:

    This work was supported by the Strategic Priority Research Program of the Chinese Academy of Sciences (No. XDA03030102).

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Lu Zhang, Yong-Wei Yang, Yuan-Guang Fu, De-Liang Fan, Yu-Cui Gao. Development and validation of the code COUPLE3.0 for the coupled analysis of neutron transport and burnup in ADS.Nuclear Science and Techniques, 2018, 29(9): 124     doi: 10.1007/s41365-018-0471-4

Abstract:

The analysis of the fuel depletion behavior is critical for maintaining the safety of accelerator-driven subcritical systems (ADSs). The code COUPLE2.0 coupling 3-D neutron transport and point burnup calculation was developed by Tsinghua University. A Monte Carlo method is used for the neutron transport analysis, and the burnup calculation is based on a deterministic method. The code can be used for the analysis of targets coupled with a reactor in ADSs. In response to additional ADS analysis requirements at the Institute of Modern Physics at the Chinese Academy of Sciences, the COUPLE3.0 version was developed to include the new functions of (1) a module for the calculation of proton irradiation for the analysis of cumulative behavior using the residual radionuclide operating history, (2) a fixed-flux radiation module for hazard assessment and analysis of the burnable poison, and (3) a module for multi-kernel parallel calculation, which improves the radionuclide replacement for the burnup analysis to balance the precision level and computational efficiency of the program. This paper introduces the validation of the COUPLE3.0 code using a fast reactor benchmark and ADS benchmark calculations. Moreover, the proton irradiation module was verified by a comparison with the analytic method of calculating the 210Po accumulation results. The results demonstrate that COUPLE3.0 is suitable for the analysis of neutron transport and the burnup of nuclides for ADSs.

Key words: COUPLE3.0, Neutron transport, Burnup, Accelerator-driven subcritical system