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题名: Development of a MCNP5 and ORIGEN2 based burnup code for molten salt reactor
作者: Sun, GM; Cheng, MS
刊名: NUCLEAR SCIENCE AND TECHNIQUES
出版日期: 2016
卷号: 27, 期号:3, 页码:-
关键词: Molten salt reactor ; Burnup ; MOCBurn ; MCNP ; ORIGEN2
DOI: 10.1007/s41365-016-0070-1
通讯作者: Sun, GM (reprint author), Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China. ; Sun, GM (reprint author), Univ Chinese Acad Sci, Beijing 100049, Peoples R China.
文章类型: 期刊论文
英文摘要: The Molten Salt Reactor (MSR) is one of the six advanced reactor nuclear energy systems for further research and development selected by Generation IV International Forum (GIF), which is distinguished by its core in which the fuel is dissolved in molten fluoride salt. Because fuel flow in the primary loop, the depletion of MSR is different from that of solid-fuel reactors. In this paper, an MCNP5 and ORIGEN2 Coupled Burnup (MOCBurn) code for MSR is developed under the MATLAB platform. Some new methods and novel arrangements are used to make it suitable for fuel flow in the MSR. To consider the fuel convection and diffusion in the primary loop of MSR, fuel mixing calculation is carried out after each burnup time step. Modeling function for geometry with repeat structures is implicated for reactor analysis with complex structures. Calculation for a high-burnup reactor pin cell benchmark is performed using the MOCBurn code. Results of depletion study show that the MOCBurn code is suitable for the traditional solid-fuel reactors. A preliminary study of the fuel mixture effect in MSR is also carried out.
收录类别: SCI
语种: 英语
WOS记录号: WOS:000380038900016
ISSN号: 1001-8042
Citation statistics:
内容类型: 期刊论文
URI标识: http://ir.sinap.ac.cn/handle/331007/26474
Appears in Collections:中科院上海应用物理研究所2011-2017年_期刊论文

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