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

• 作 者: Zhao-Qing Liu Ze-Long Zhao Yong-Wei Yang Yu-Cui Gao Hai-Yan Meng Qing-Yu Gao
• 机 构: Institute of Modem Physics, Chinese Academy of Sciences,Lanzhou 730000, China“,”School of Nuclear Sc
• 出 处: 核技术（英文版）
• 发表日期: 2019年3期
• 关键词: ADS-coupled proton-neutron transport Burnup calculation IMPC-Burnup FLUKA OpenMC

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 buup code system called IMPC-Buup by coupling FLUKA,OpenMC,and ORIGEN2.The program is preliminarily verified by OECD-NEA pin cell and IAEA-ADS benchmarking by comparison with experimental values and calculated results from other studies.Moreover,the physics design scheme of the CLADS subcritical core is utilized to test the feasibility of IMPC-Buup program in the buup calculation of ADS system.Reference results are given by the COUPLE3.0 program.The results of IMPC-Buup show good agreement with those of COU-PLE3.0.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 buup calculation is improved when the equivalent flux method is used.Therefore,the IMPC-Bumup code is suitable for buup analysis of the ADS system.