Concept design of moderation collimator for a minitype neutron radiography system

WU Yang DOU Haifeng TANG Bin HUO Heyong

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Concept design of moderation collimator for a minitype neutron radiography system

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- Concept design of moderation collimator for a minitype neutron radiography system
- NUCLEAR TECHNIQUES Vol. 34, Issue 10, (2011)
- 作者机构：
  
  中国工程物理研究院核物理与化学研究所
- 作者简介：
- 基金信息：
- DOI：
  CLC： O571.53
- Published：01 October 2011
- 稿件说明：
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[1]吴洋,霍合勇,刘斌,孙勇,唐彬.小型源热中子照相装置准直慢化系统设计[J].核技术,2011,34(10):755-758.

WU Yang DOU Haifeng TANG Bin HUO Heyong. Concept design of moderation collimator for a minitype neutron radiography system[J]. Nuclear techniques, 2011, 34(10): 755-758.
[1]吴洋,霍合勇,刘斌,孙勇,唐彬.小型源热中子照相装置准直慢化系统设计[J].核技术,2011,34(10):755-758. DOI：

WU Yang DOU Haifeng TANG Bin HUO Heyong. Concept design of moderation collimator for a minitype neutron radiography system[J]. Nuclear techniques, 2011, 34(10): 755-758. DOI：

摘要

小型中子源中子照相技术具有便携性强

应用范围广的优点

在检测一些较大或难以移动的样品时较固定式（反应堆中子源）中子照相系统具有优势。采用MCNP软件对一小型中子源中子照相装置的热中子准直屏蔽系统进行了理论设计

确定中子慢化体由238U和聚乙烯构成

辅以石墨反射层和硼聚乙烯吸收层

经优化计算

预计成像处热注量率达104 cm-2.s-1以上、准直比30、成像视场20 cm×20 cm、镉比20。

Abstract

For designing a minitype neutron radiography system

which is advantageous in detecting large or irremovable objects.a shielding collimator was simulated with the MCNP code.U-238 and high density polyethylene were chosen to moderate 14 MeV neutrons to 3 MeV.Graphite and CH-B were used as reflect layer and shielding layer

respectively.With the optimized design parameters

as the results show

the neutron radiography system can provide a neutron flux of up to 104 cm?2.s?1

with L/D = 30

imaging area = 20 cm×20 cm

and Cd radio = 20.

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