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基于MCNPX代码对德黑兰研究堆进行快中子放射性核素生产的新设计研究。

Study on a new design of Tehran Research Reactor for radionuclide production based on fast neutrons using MCNPX code.

作者信息

Zandi Nadia, Afarideh Hossein, Aboudzadeh Mohammad Reza, Rajabifar Saeed

机构信息

Department of Energy engineering and Physics, Amirkabir University of Technology, Tehran, Iran.

Department of Energy engineering and Physics, Amirkabir University of Technology, Tehran, Iran.

出版信息

Appl Radiat Isot. 2018 Feb;132:67-71. doi: 10.1016/j.apradiso.2017.11.006. Epub 2017 Nov 6.

DOI:10.1016/j.apradiso.2017.11.006
PMID:29169062
Abstract

The aim of this work is to increase the magnitude of the fast neutron flux inside the flux trap where radionuclides are produced. For this purpose, three new designs of the flux trap are proposed and the obtained fast and thermal neutron fluxes compared with each other. The first and second proposed designs were a sealed cube contained air and DO, respectively. The results of calculated production yield all indicated the superiority of the latter by a factor of 55% in comparison to the first proposed design. The third proposed design was based on changing the surrounding of the sealed cube by locating two fuel plates near that. In this case, the production yield increased up to 70%.

摘要

这项工作的目的是提高产生放射性核素的通量阱内快中子通量的强度。为此,提出了通量阱的三种新设计,并将得到的快中子通量和热中子通量进行了相互比较。提出的第一种和第二种设计分别是一个密封的装有空气和重水的立方体。所有计算得出的产率结果均表明,与第一种提出的设计相比,后者的优势高出55%。提出的第三种设计是基于在密封立方体周围放置两块燃料板来改变其周围环境。在这种情况下,产率提高了70%。

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