Development of a MCNP5 and ORIGEN2 based burnup code for molten salt reactor
文献类型：期刊论文
| 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 |
| ISSN号 | 1001-8042 |
| 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. |
| 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 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/26474]  |
| 专题 | 上海应用物理研究所_中科院上海应用物理研究所2011-2017年 |
| 推荐引用方式 GB/T 7714 | Sun, GM,Cheng, MS. Development of a MCNP5 and ORIGEN2 based burnup code for molten salt reactor[J]. NUCLEAR SCIENCE AND TECHNIQUES,2016,27(3):-. |
| APA | Sun, GM,&Cheng, MS.(2016).Development of a MCNP5 and ORIGEN2 based burnup code for molten salt reactor.NUCLEAR SCIENCE AND TECHNIQUES,27(3),-. |
| MLA | Sun, GM,et al."Development of a MCNP5 and ORIGEN2 based burnup code for molten salt reactor".NUCLEAR SCIENCE AND TECHNIQUES 27.3(2016):-. |
入库方式： OAI收割
来源：上海应用物理研究所
浏览0
下载0
收藏0
其他版本
除非特别说明，本系统中所有内容都受版权保护，并保留所有权利。