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

作者：Zhang, Lu; Yang, Yong-Wei^*; Fu, Yuan-Guang; Fan, De-Liang; Gao, Yu-Cui

来源：Nuclear Science and Techniques, 2018, 29(9): 124.

DOI：10.1007/s41365-018-0471-4

• COUPLE3.0
• Neutron transport
• Burnup
• Accelerator-driven subcritical system

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 Po-210 accumulation results. The results demonstrate that COUPLE3.0 is suitable for the analysis of neutron transport and the burnup of nuclides for ADSs.

• 出版日期2018-9
• 单位中国科学院大学; 中国科学院近代物理研究所; 中国工程物理研究院; 北京应用物理与计算数学研究所