掺重晶石粉末的水泥基中子及γ屏蔽材料实验研究
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- 英文论文题名：Experiment research on cement-based neutron and gamma shielding material mixed with Barite powder
- 论文作者：沈志强 ; 康青 ; 王正刚
- 英文论文作者：SHEN Zhi-qiang ; KANG Qing ; WANG Zheng-gang ; Logistical Engineering University of PLA
- 年：2015
- 作者机构：后勤工程学院;
- 论文关键词：14.8 MeV快中子 ; ~(252)Cf中子 ; ~(60)Co源γ射线 ; 重晶石 ; 中子屏蔽
- 英文论文关键词：14.8 MeV fast neutron ; ~(252)Cf neutron ; ~(60)Co gamma rays ; barite ; neutron shielding
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第5册（核材料分卷、辐射防护分卷）
- 语种：中文
- 分类号：TB34
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：4
- 文件大小：257k
- 原文格式：O
- 会议级别：全国
摘要
采用平均粒径为26μm的重晶石粉末为超细集料,按体积替换砂集料的10%,20%,30%,使用普通砂浆工艺制备了φ10.5 cm×6 cm~2的圆柱形中子及γ防护实验样品。采用5SDH-2串列加速器D-T中子源、~(252)Cf中子源与长计数器组成的实验系统,获得了各样品对14.8 MeV、2.13 MeV快中子注量穿透率;采用PTW UNDOS计量仪和~(60)Co组成的测试系统,评价了样品对1.33 MeVγ射线的屏蔽性能。结果表明,6 cm厚度的实验样品,随着重晶石粉末掺加量的增加,14.8 MeV快中子穿透率从普通砂浆的58.8%增加到高掺量样品的62.5%;2.13 MeV的~(252)Cf中子穿透率则从普通砂浆的37.8%减小到34.4%;1.33 MeV的γ射线穿透率从54.5%小幅下降为约52%。因此,掺混重晶石粉末的水泥基材料适合作为放射性核素中子源的屏蔽材料,而不适合D-T中子源的防护处理。
Using barite as ultra fine aggregate powder average particle size of 26 μm,by volume replacement sand aggregate 10%,20%,30%,φ10.5 cm × 6 cm cylindrical neutron and gamma protection experimental samples using ordinary mortar preparation process.The experimental system is composed of the 5SDH-2 tandem accelerator neutron source D-T and ~(252)Cf neutron source and the long counter,for each sample for 14.8 MeV and the 2.13 MeV fast neutron fluency rate of penetration;test system using PTW UNDOS meter and ~(60)Co components,shielding performance of samples for 1.33 MeV gamma rays evaluation.Results show that the experimental samples of 6 cm thickness,along with the increase of barite powder dosage,14.8 MeV fast neutron penetration rate increased from 58.8%to 62.5%of high content sample;~(252)Cf neutron 2.13 MeV penetration rate decreased from 37.8% to 34.4%;gamma ray 1.33 MeV penetration rate decreased slightly from 54.5% to 52%.Therefore,cement base material mixing barite powder suitable for shielding materials radionuclide neutron source,and not suitable for the protection treatment of D-T neutron source.
Using barite as ultra fine aggregate powder average particle size of 26 μm,by volume replacement sand aggregate 10%,20%,30%,φ10.5 cm × 6 cm cylindrical neutron and gamma protection experimental samples using ordinary mortar preparation process.The experimental system is composed of the 5SDH-2 tandem accelerator neutron source D-T and ~(252)Cf neutron source and the long counter,for each sample for 14.8 MeV and the 2.13 MeV fast neutron fluency rate of penetration;test system using PTW UNDOS meter and ~(60)Co components,shielding performance of samples for 1.33 MeV gamma rays evaluation.Results show that the experimental samples of 6 cm thickness,along with the increase of barite powder dosage,14.8 MeV fast neutron penetration rate increased from 58.8%to 62.5%of high content sample;~(252)Cf neutron 2.13 MeV penetration rate decreased from 37.8% to 34.4%;gamma ray 1.33 MeV penetration rate decreased slightly from 54.5% to 52%.Therefore,cement base material mixing barite powder suitable for shielding materials radionuclide neutron source,and not suitable for the protection treatment of D-T neutron source.
引文
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[2]A.El-Sayed Abdo.Calculation of the cross-sections for fast neutrons and gamma-rays in concrete shields[J].Annals Of Nuclear Energy,2002,29:1977-1978.
[3]M.H.Kharita,S.Yousef,et al.The effect of carbon powder addition on the properties of hematite radiation shielding concrete[J].Progress in Nuclear Energy,2009,51:388-392.
[4]Urgay Korkut,Adem Un,et al.Neutron dose transmission measurements for several new concrete samples including colemanite[J].Annals Of Nuclear Energy,2010,37:996-998.
[5]TAtsuhiko Morioka,Satoshi Sato,et al.Irradiation and penetration tests of boron-doped low activation concrete using 2.45 and 14 MeV neutron sources[J].Journal of Nuclear Materials,2004:1619-1623.
[6]王萍,王福川.防辐射混凝土的试验研究[J].建筑材料学报,2000,3(6):182-186.
[7]伍崇明,丁德馨等.高密度混凝土辐射屏蔽试验研究与应用[J].原子能科学技术,2008,42(10):956-960.
[8]刘群贤.补偿收缩重混凝土在核电站乏燃料后处理工程中的应用[J].核工程研究与设计,2004,48:37-40.
[9]曾志献.大体积防中子辐射特种混凝土墙体结构施工技术[J].建筑技术,2003,34(7):515-516.
[10]雷昌聚.岭澳核电站混凝土的配合比设计与施工[J].建筑技术,2002,33(1):44-45.
[11]Jun Xu,Qing Kang,Zhiqiang Shen,et al.Measurements of 14.8 MeV Fast Neutron Attenuation of CementBarite Composites[R].Proceedings of 2011 China Functional Materials Technology and Industry Forum VolumeⅢ,2011:964-966.