Preparation of an Ultra-Thin, Highly Filled, Neutron-Shielding Material

Xin Peng Hou; Shu Feng Li; Yan Chen; Di Xu; Wei Tang

doi:10.4028/www.scientific.net/MSF.815.616

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HomeMaterials Science ForumMaterials Science Forum Vol. 815Preparation of an Ultra-Thin, Highly Filled,...

Preparation of an Ultra-Thin, Highly Filled, Neutron-Shielding Material

Abstract:

We develop an ultra-thin, highly filled, neutron-shielding material. This material exhibits a desirable neutron-shielding performance, and also has certain advantageous mechanical properties and uses. We study the physical properties of shielding materials with different polyolefins as base materials, and investigate the neutron-shielding performance of boron-containing and lithium-containing shielding materials. We furthermore report on the effect of additive amounts of functional additives on shielding properties and physical-chemical properties. We additionally study the effect of radiation crosslinking technology on shielding material properties. We show that, using ethylene-octene copolymer (POE) modified low-density polyethylene (PE-LD), the additive amounts of boron carbide (B₄C) and nano-montmorillonite (OMMT) are 60–70% and 4%, respectively. The optimal radiation dose is 160 kGy, and the shielding materials exhibit good neutron-shielding performance and mechanical strength.

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Materials Science Forum (Volume 815)

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616-621

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https://doi.org/10.4028/www.scientific.net/MSF.815.616

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Online since:

March 2015

Authors:

Xin Peng Hou*, Shu Feng Li, Yan Chen, Di Xu, Wei Tang

Keywords:

Highly Filled, Neutron Shielding, Radiation Crosslinking, Ultra Thin

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