Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2019, Vol. 30 ›› Issue (3): 44 doi: 10.1007/s41365-019-0560-z

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Development and validation of depletion code system IMPC-Burnup for ADS

Zhao-Qing Liu1,2 • Ze-Long Zhao1,2 • Yong-Wei Yang1,2 • Yu-Cui Gao1 • Hai-Yan Meng1 • Qing-Yu Gao1,2   

  1. 1 Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
    2 School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2018-04-23 Revised:2018-07-03 Accepted:2018-07-11
  • Contact: Ze-Long Zhao; Yong-Wei Yang;
  • Supported by:
    This work was supported by the ‘‘Strategic Priority Research Program’’ of Chinese Academy of Sciences (No.XDA03030102).
PDF ShareIt Export Citation
Zhao-Qing Liu, Ze-Long Zhao, Yong-Wei Yang, Yu-Cui Gao, Hai-Yan Meng, Qing-Yu Gao. Development and validation of depletion code system IMPC-Burnup for ADS.Nuclear Science and Techniques, 2019, 30(3): 44     doi: 10.1007/s41365-019-0560-z

Abstract: Depletion calculation is important for studying the transmutation efficiency of minor actinides and longlife fission products in accelerator-driven subcritical reactor system (ADS). Herein the Python language is used to develop a burnup code system called IMPC-Burnup by coupling FLUKA, OpenMC, and ORIGEN2. The program is preliminarily verified by OECD-NEA pin cell and IAEAADS benchmarking by comparison with experimental values and calculated results from other studies. Moreover, the physics design scheme of the CIADS subcritical core is utilized to test the feasibility of IMPC-Burnup program in the burnup calculation of ADS system. Reference results are given by the COUPLE3.0 program. The results of IMPC-Burnup show good agreement with those of COUPLE3.0. In addition, since the upper limit of the neutron transport energy for OpenMC is 20 MeV, neutrons with energies greater than 20 MeV in the CIADS subcritical core cannot be transported; thus, an equivalent flux method has been proposed to consider neutrons above 20 MeV in the OpenMC transport calculation. The results are compared to those that do not include neutrons greater than 20 MeV. The conclusion is that the accuracy of the actinide nuclide mass in the burnup calculation is improved when the equivalent flux method is used. Therefore, the IMPC-Burnup code is suitable for burnup analysis of the ADS system.

Key words: ADS-coupled proton–neutron transport, Burnup calculation, IMPC-Burnup, FLUKA, OpenMC, ORIGEN2