Study on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation
In this research, a high-boron-content composite material with both neutron and γ rays shielding properties was developed by an optimized design and manufacture. It consists of 304 stainless steel as the matrix and spherical boron carbide (B<sub>4</sub>C) particles as the functional part...
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MDPI AG
2021
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oai:doaj.org-article:b730a4bd06934453890d6c7ffc0c21752021-11-25T18:15:37ZStudy on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation10.3390/ma142270041996-1944https://doaj.org/article/b730a4bd06934453890d6c7ffc0c21752021-11-01T00:00:00Zhttps://www.mdpi.com/1996-1944/14/22/7004https://doaj.org/toc/1996-1944In this research, a high-boron-content composite material with both neutron and γ rays shielding properties was developed by an optimized design and manufacture. It consists of 304 stainless steel as the matrix and spherical boron carbide (B<sub>4</sub>C) particles as the functional particles. The content of B<sub>4</sub>C is 24.68 wt%, and the particles’ radius is 1.53 mm. The density of the newly designed material is 5.17 g·cm<sup>−3</sup>, about 68.02% of that of traditional borated stainless steel containing 1.7 wt% boron, while its neutrons shielding performance is much better. Firstly, focusing on shielding properties and material density, the content and the size of B<sub>4</sub>C were optimized by the Genetic Algorithm (GA) program combined with the MCNP program. Then, some samples of the material were manufactured by the infiltration casting technique according to the optimized results. The actual density of the samples was 5.21 g cm<sup>−3</sup>. In addition, the neutron and γ rays shielding performance of the samples and borated stainless steel containing 1.7 wt% boron was tested by using an <sup>241</sup>Am–Be neutron source and <sup>60</sup>Co and <sup>137</sup>Cs γ rays sources, respectively, and the results were compared. It can be concluded that the new designed material could be used as a material for nuclear power plants or spent-fuel storage and transportation containers with high requirements for mobility.Wei-Qiang SunGuang HuXiao-Hang YuJian ShiHu XuRong-Jun WuChao HeQiang YiHua-Si HuMDPI AGarticleradiation-shielding materialoptimization designMCNP codeneutronγ rays transmission experimentTechnologyTElectrical engineering. Electronics. Nuclear engineeringTK1-9971Engineering (General). Civil engineering (General)TA1-2040MicroscopyQH201-278.5Descriptive and experimental mechanicsQC120-168.85ENMaterials, Vol 14, Iss 7004, p 7004 (2021) |
| institution |
DOAJ |
| collection |
DOAJ |
| language |
EN |
| topic |
radiation-shielding material optimization design MCNP code neutron γ rays transmission experiment Technology T Electrical engineering. Electronics. Nuclear engineering TK1-9971 Engineering (General). Civil engineering (General) TA1-2040 Microscopy QH201-278.5 Descriptive and experimental mechanics QC120-168.85 |
| spellingShingle |
radiation-shielding material optimization design MCNP code neutron γ rays transmission experiment Technology T Electrical engineering. Electronics. Nuclear engineering TK1-9971 Engineering (General). Civil engineering (General) TA1-2040 Microscopy QH201-278.5 Descriptive and experimental mechanics QC120-168.85 Wei-Qiang Sun Guang Hu Xiao-Hang Yu Jian Shi Hu Xu Rong-Jun Wu Chao He Qiang Yi Hua-Si Hu Study on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation |
| description |
In this research, a high-boron-content composite material with both neutron and γ rays shielding properties was developed by an optimized design and manufacture. It consists of 304 stainless steel as the matrix and spherical boron carbide (B<sub>4</sub>C) particles as the functional particles. The content of B<sub>4</sub>C is 24.68 wt%, and the particles’ radius is 1.53 mm. The density of the newly designed material is 5.17 g·cm<sup>−3</sup>, about 68.02% of that of traditional borated stainless steel containing 1.7 wt% boron, while its neutrons shielding performance is much better. Firstly, focusing on shielding properties and material density, the content and the size of B<sub>4</sub>C were optimized by the Genetic Algorithm (GA) program combined with the MCNP program. Then, some samples of the material were manufactured by the infiltration casting technique according to the optimized results. The actual density of the samples was 5.21 g cm<sup>−3</sup>. In addition, the neutron and γ rays shielding performance of the samples and borated stainless steel containing 1.7 wt% boron was tested by using an <sup>241</sup>Am–Be neutron source and <sup>60</sup>Co and <sup>137</sup>Cs γ rays sources, respectively, and the results were compared. It can be concluded that the new designed material could be used as a material for nuclear power plants or spent-fuel storage and transportation containers with high requirements for mobility. |
| format |
article |
| author |
Wei-Qiang Sun Guang Hu Xiao-Hang Yu Jian Shi Hu Xu Rong-Jun Wu Chao He Qiang Yi Hua-Si Hu |
| author_facet |
Wei-Qiang Sun Guang Hu Xiao-Hang Yu Jian Shi Hu Xu Rong-Jun Wu Chao He Qiang Yi Hua-Si Hu |
| author_sort |
Wei-Qiang Sun |
| title |
Study on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation |
| title_short |
Study on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation |
| title_full |
Study on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation |
| title_fullStr |
Study on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation |
| title_full_unstemmed |
Study on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation |
| title_sort |
study on a high-boron-content stainless steel composite for nuclear radiation |
| publisher |
MDPI AG |
| publishDate |
2021 |
| url |
https://doaj.org/article/b730a4bd06934453890d6c7ffc0c2175 |
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