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

doi:10.1007/s41365-019-0560-z

	Development and validation of depletion code system IMPC-Burnup for ADS
	Yang, Yong-Wei 1,2; Gao, Qing-Yu 1,2; Liu, Zhao-Qing 1,2; Zhao, Ze-Long 1,2; Meng, Hai-Yan 2; Gao, Yu-Cui 2
刊名	NUCLEAR SCIENCE AND TECHNIQUES
	2019-03-01
卷号	30 期号:3 页码:10
关键词	ADS-coupled proton-neutron transport Burnup calculation IMPC-Burnup FLUKA OpenMC ORIGEN2
ISSN号	1001-8042
DOI	10.1007/s41365-019-0560-z
通讯作者	Zhao, Ze-Long(zhaozelong@impcas.ac.cn) ; Yang, Yong-Wei(yangyongwei@impcas.ac.cn)
英文摘要	Depletion calculation is important for studying the transmutation efficiency of minor actinides and long-life 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 IAEA-ADS 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.
资助项目	Strategic Priority Research Program of Chinese Academy of Sciences[XDA03030102]
WOS研究方向	Nuclear Science & Technology ; Physics
语种	英语
出版者	SPRINGER SINGAPORE PTE LTD
WOS记录号	WOS:000462284000009
资助机构	Strategic Priority Research Program of Chinese Academy of Sciences
内容类型	期刊论文
源URL	[http://119.78.100.186/handle/113462/133860]
专题	中国科学院近代物理研究所
通讯作者	Yang, Yong-Wei; Zhao, Ze-Long
作者单位	1.Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China 2.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Gansu, Peoples R China
推荐引用方式 GB/T 7714	Yang, Yong-Wei,Gao, Qing-Yu,Liu, Zhao-Qing,et al. Development and validation of depletion code system IMPC-Burnup for ADS[J]. NUCLEAR SCIENCE AND TECHNIQUES,2019,30(3):10.
APA	Yang, Yong-Wei,Gao, Qing-Yu,Liu, Zhao-Qing,Zhao, Ze-Long,Meng, Hai-Yan,&Gao, Yu-Cui.(2019).Development and validation of depletion code system IMPC-Burnup for ADS.NUCLEAR SCIENCE AND TECHNIQUES,30(3),10.
MLA	Yang, Yong-Wei,et al."Development and validation of depletion code system IMPC-Burnup for ADS".NUCLEAR SCIENCE AND TECHNIQUES 30.3(2019):10.