掺氧化钨对水泥基材料γ射线屏蔽性能的影响
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摘要
分别以黄色和蓝色氧化钨微粉为细集料,采用水泥基集料掺混方法制备了?10.5 cm×6.0 cm规格圆柱形样品,并通过PTW UNDOS标准计量仪和~(60)Co-γ、~(137)Cs-γ源组成的实验系统测试了材料对1.25,0.66 MeV射线的屏蔽性能。结果表明:同样6 cm厚度规格,普通样品~(60)Co-γ射线穿透率为54.3%,~(137)Cs-γ射线穿透率为42.5%;而掺混体积分数为30%黄色氧化钨样品的~(60)Co-γ射线穿透率下降为37.0%,~(137)Cs-γ射线穿透率下降为26.9%;掺混体积分数为20%蓝色氧化钨样品的~(60)Co-γ穿透率则下降为41.5%,~(137)Cs-γ射线穿透率下降为29.7%。因此,掺加氧化钨可以增强水泥基材料对γ射线的屏蔽性能。
The samples of γ rays shielding cement-based material(size:?10.5 cm×6.0 cm)were prepared by using cement-based aggregate blending method with yellow and blue tungsten oxide powder as fine aggregate, then the shielding performance of 1.25 Me V-γ rays and 0.66 Me V-γ rays were tested by experimental system which was composed of PTW UNDOS measuring instru-ment and ~(60)Co-γ source or ~(137)Cs-γ source. The results showed that,when yellow tungsten oxide's volume fraction was 30%,the ~(60)Co-γ rays and ~(137)Cs-γ rays transmittance(h=6 cm)was decreased from 54.3% to 37.0%,and from 42.5% to 26.9%; on the other hand,when blue tungsten oxide's volume fraction was 20%, the ~(60)Co-γ rays and ~(137)Cs-γ rays transmittance of same size samples was de-creased from 54.3% to 41.5%,and from 42.5% to 29.7%. Therefore, blending tungsten oxide can enhance the cement-based materi-als on the γ-ray shielding performance.
The samples of γ rays shielding cement-based material(size:?10.5 cm×6.0 cm)were prepared by using cement-based aggregate blending method with yellow and blue tungsten oxide powder as fine aggregate, then the shielding performance of 1.25 Me V-γ rays and 0.66 Me V-γ rays were tested by experimental system which was composed of PTW UNDOS measuring instru-ment and ~(60)Co-γ source or ~(137)Cs-γ source. The results showed that,when yellow tungsten oxide's volume fraction was 30%,the ~(60)Co-γ rays and ~(137)Cs-γ rays transmittance(h=6 cm)was decreased from 54.3% to 37.0%,and from 42.5% to 26.9%; on the other hand,when blue tungsten oxide's volume fraction was 20%, the ~(60)Co-γ rays and ~(137)Cs-γ rays transmittance of same size samples was de-creased from 54.3% to 41.5%,and from 42.5% to 29.7%. Therefore, blending tungsten oxide can enhance the cement-based materi-als on the γ-ray shielding performance.
引文
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[16]Akkurt I,Akyildirim H,Mavi B,et al.Gammy-ray shielding properties of concrete including barite at different energies[J].Annals of Nuclear Energy,2010,52(7):620-623.
[2]谯华,周从直,敖漉,等.核污染的危害及其去除方法[J].后勤工程学院学报,2007,23(1):66-69.Qiao Hua,Zhou Cong-zhi,Ao Lu,et al.The harm and removal methods of nuclear pollution[J].Journal of Logistical Engineering University,2007,23(1):66-69.
[3]徐军,康青,沈志强,等.核防护用水泥基中子屏蔽材料的研究进展[J].材料开发与应用,2011,26(5):92-95.Xu Jun,Kang Qing,Shen Zhi-qiang,et al.Progress of cement-based neutron shielding materials in nuclear protecting[J].Development and Application of Materials,2011,26(5):92-95.
[4]Bashter I I,Abdo A E,Makarious A S,et al.A comparative of the attenuation of reactor thermal neutrons in different types of concrete[J].Annals of Nuclear Energy,1996,23(14):1189-1195.
[5]Abdo A E.Calculation of the cross-sections for fast neutrons and gamma-rays in concrete shields[J].Annals of Nuclear Energy,2002,29(16):1977-1988.
[6]Kharita M H,Yousef S,Alnassar M.The effect of carbon powder addition on the properties of hematite radiation shielding concrete[J].Progress in Nuclear Energy,2009,51(2):388-392.
[7]Korkut T,ün A,Demir F,et al.Neutron dose transmission measurements for several new concrete samples including colemanite[J].Annals of Nuclear Energy,2010,37(7):996-998.
[8]Morioka A,Sato S,Kinno M,et al.Irradiation and penetration tests of boron-doped low activation concrete using 2.45 and 14 Me V neutron sources[J].Journal of Nuclear Materials,2004,329-333:1619-1623.
[9]丁庆军,张立华,胡曙光,等.防辐射混凝土及核固化材料研究现状与发展[J].武汉理工大学学报,2002,24(2):16-19.Ding Qing-jun,Zhang Li-hua,Hu Shu-guang,et al.The research situation of anti-radioactive concrete and solid fid materials for the nuclear wastes[J].Journal of Wuhan University of Technology,2002,24(2):16-19.
[10]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(2):182-186.Wang Ping,Wang Fu-chuan.Experimental study on the properties of radiation shield concrete[J].Journal of Building Materials,2000,3(2):182-186.
[11]刘显坤,刘颖,唐杰,等.辐射屏蔽材料的研究进展[J].材料导报,2006,20(6):22-25.Liu Xian-kun,Liu Ying,Tang Jie,et al.The advance in study in radiation-proof shielding material[J].Materials Review,2006,20(6):22-25.
[12]伍崇明,丁德馨,肖雪夫,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.Wu Chong-ming,Ding De-xin,Xiao Xue-fu,et al.Study on application of high-density concrete in radiation-shielding experiment[J].Atomic Energy Science and Technology,2008,42(10):956-960.
[13]何建洪,孙勇,段永华,等.射线与中子辐射屏蔽材料的研究进展[J].材料导报,2011,25(18):347-351.He Jian-hong,Sun Yong,Duan Yong-hua,et al.Research progress of ray and neutron radiation shielding material[J].Materials Review,2011,25(18):347-351.
[14]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.Lei Chang-ju.Concrete mix proportion design for shielded wall of Lingao nuclear power plant and its construction[J].Architecture Technology,2002,33(1):44-45.
[15]何莉莉.一种新型材料对γ射线的屏蔽性能研究[D].成都:成都理工大学,2009.
[16]Akkurt I,Akyildirim H,Mavi B,et al.Gammy-ray shielding properties of concrete including barite at different energies[J].Annals of Nuclear Energy,2010,52(7):620-623.