Neutron radiation shielding with PUR composites loaded with B4C or graphite

被引：6
|
作者：
Cataldo, Franco [1 ]
Prata, Michele [2 ]
机构：
[1] Actinium Chem Res Inst, Via Casilina 1626A, I-00133 Rome, Italy
[2] Univ Pavia, Lab Energia Nucl Applicata, Via Aselli, Pavia, Italy
来源：
FULLERENES NANOTUBES AND CARBON NANOSTRUCTURES | 2019年 / 27卷 / 07期
关键词：
Thermal neutrons; radiation shielding; polyurethane composites; boron carbide; graphite; HE+ ION-BOMBARDMENT; FT-IR; C-70; FULLERENES; C-60; B12C3; DSC;
D O I：
10.1080/1536383X.2019.1604512
中图分类号：
O64 [物理化学（理论化学）、化学物理学];
学科分类号：
070304 ; 081704 ;
摘要：
The thermal neutron radiation shielding effectiveness of polyurethane (PUR) composites loaded with 20.9% by weight of boron carbide or by 20.4% graphite micronized fillers was evaluated. As expected, the former composite was found very effective in thermal neutron radiation shielding, and its performances were compared with those of other PUR composites loaded with about 20% of amorphous boron or 20% boron nitride. On the other hand the PUR composite loaded with graphite was found not suitable for shielding thermal neutrons. FT-IR spectroscopy and DSC were used to demonstrate the excellent neutron radiation resistance of the PUR composites of this study.
引用
收藏
页码：531 / 537
页数：7
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