Enhancement of thermal neutron shielding of cement mortar by using borosilicate glass powder

被引:24
作者
Jang, Bo-Kil [1 ]
Lee, Jun-Cheol [2 ]
Kim, Ji-Hyun [1 ]
Chung, Chul-Woo [1 ]
机构
[1] Pukyong Natl Univ, Busan 48513, South Korea
[2] Kyungpook Natl Univ, Daegu 41566, South Korea
关键词
Borosilicate glass powder; Pozzolanic reaction; Compressive strength; Neutron shielding; WASTE GLASS; DIFFUSION; CONCRETE;
D O I
10.1016/j.apradiso.2017.01.047
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
Concrete has been used as a traditional biological shielding material. High hydrogen content in concrete also effectively attenuates high-energy fast neutrons. However, concrete does not have strong protection against thermal neutrons because of the lack of boron compound. In this research, boron was added in the form of borosilicate glass powder to increase the neutron shielding property of cement mortar. Borosilicate glass powder was chosen in order to have beneficial pozzolanic activity and to avoid deleterious expansion caused by an alkali silica reaction. According to the experimental results, borosilicate glass powder with an average particle size of 13 mu m showed pozzolanic activity. The replacement of borosilicate glass powder with cement caused a slight increase in the 28-day compressive strength. However, the incorporation of borosilicate glass powder resulted in higher thermal neutron shielding capability. Thus, borosilicate glass powder can be used as a good mineral additive for various radiation shielding purposes.
引用
收藏
页码:1 / 5
页数:5
相关论文
共 15 条
[1]   Dissolution and growth of spinel crystals in a borosilicate glass [J].
Alton, J ;
Plaisted, TJ ;
Hrma, P .
JOURNAL OF NON-CRYSTALLINE SOLIDS, 2002, 311 (01) :24-35
[2]  
Davis H.S., 1972, ACI SP, V34, P1109
[3]  
Davraz M, 2015, ACTA PHYS POL A, V128, pB26, DOI [10.12693/APhysPolA.127.B-26, 10.12693/APhysPolA.128.B-26]
[4]   Review on the addition of boron compounds to radiation shielding concrete [J].
Kharita, M. H. ;
Yousef, S. ;
AlNassar, M. .
PROGRESS IN NUCLEAR ENERGY, 2011, 53 (02) :207-211
[5]   Rhenium Solubility in Borosilicate Nuclear Waste Glass: Implications for the Processing and Immobilization of Technetium-99 [J].
McCloy, John S. ;
Riley, Brian J. ;
Goel, Ashutosh ;
Liezers, Martin ;
Schweiger, Michael J. ;
Rodriguez, Carmen P. ;
Hrma, Pavel ;
Kim, Dong-Sang .
ENVIRONMENTAL SCIENCE & TECHNOLOGY, 2012, 46 (22) :12616-12622
[6]  
Mehta P.K., 2017, CONCRETE MICROSTRUCT
[7]   Effect of barium on diffusion of sodium in borosilicate glass [J].
Mishra, R. K. ;
Kumar, Sumit ;
Tomar, B. S. ;
Tyagi, A. K. ;
Kaushik, C. P. ;
Raj, Kanwar ;
Manchanda, V. K. .
JOURNAL OF HAZARDOUS MATERIALS, 2008, 156 (1-3) :129-134
[8]   Physico-chemical characteristics of chemically activated cement containing boron [J].
Olgun, A. ;
Kavas, T. ;
Erdogan, Y. ;
Once, G. .
BUILDING AND ENVIRONMENT, 2007, 42 (06) :2384-2395
[9]  
Rinard P., 1991, Passive Nondestructive Assay of Nuclear Materials
[10]   Studies on concrete containing ground waste glass [J].
Shao, YX ;
Lefort, T ;
Moras, S ;
Rodriguez, D .
CEMENT AND CONCRETE RESEARCH, 2000, 30 (01) :91-100