Advanced SearchSearch Tips
Neutron Shielding Performance of Mortar Containing Synthetic High Polymers and Boron Carbide
facebook(new window)  Pirnt(new window) E-mail(new window) Excel Download
 Title & Authors
Neutron Shielding Performance of Mortar Containing Synthetic High Polymers and Boron Carbide
Min, Ji-Young; Lee, Bin-Na; Lee, Jong-Suk; Lee, Jang-Hwa;
  PDF(new window)
Concrete walls of neutron generating facilities such as fusion reactors and fission reactors become radioactive by neutron irradiation. Both low-activation and neutron shielding are a critical concern at the dismantling stage after the shutdown of facilities with a requirement of radioactive waste management. To tackle this, two types of additives were investigated in fabricating mortar specimens: synthetic high polymers and boron carbide. It is well known that a hydrogen atom is effective in neutron shielding by an elastic scattering because its mass is almost the same as that of the neutron. And boron is an effective neutron absorber with a big neutron absorption cross section. In this study, the effect of the type, shape, and size of polymers were investigated as well as that of boron carbide. Total 16 mix designs were prepared to reveal the effect of polymers on mechanical properties and neutron shielding performance. The neutron does equivalent of polymers-based mortar for fast neutrons decreased by 36 %, and the count rate of boron carbide-based mortar with regard to thermal neutrons decreased by 90 % compared to conventional mortar. These results showed that a combination of polymers and boron carbide compounds has potential to reduce the thickness of neutron shields as well as radioactive waste from reactors.
neutron shielding;low-activation;synthetic high polymers;boron carbide;mortar;
 Cited by
Akkurt, I., Basyigit, C., Kilincarslan, S., Mavi, B., and Akkurt, A., "Radiation Shielding of Concretes Containing Different Aggregates", Cement and Concrete Composites, Vol.28, Issue 2, 2006, pp.153-157. crossref(new window)

Basyigit, C., Uysal, V., Kilincarslan, S., Mavi, B., Gunoglu, K., Akkurt, I., and Akkas, A., "Investigating Radiation Shielding Properties of Different Mineral Origin Heavyweight Concretes", AIP conference proceedings, Vol.1400, 2011, pp.232-235.

Lee, J. Y., "Development and Application of Low-Activation Cement", Cement, Vol.188, 2010, pp.27-37.

Halverson, D. C., Pysik, A. J., Aksay, I. A., and Snowden, W. E., "Processing of boron carbide-aluminum composites", Journal of the American Ceramic Society, Vol.72, 1989, pp.775-780. crossref(new window)

Sandia Laboratories Transportation Technology Center, "Development of Boron Carbide-Copper Cermets: Status Report", Department of Energy, Report SAND-78-2317, 1979, p.58.

Sato., S., Maegawa, T., Yoshimatsu, K., Sato, K., Nonaka, A., Takakura, K., Ochiai, K., and Konno, C., "Development of a low activation concrete shielding wall by multi-layered structure for a fusion reactor", Journal of Nuclear Materials, Vol.417, No.1-3, 2011, pp.1131-1134. crossref(new window)

Cho, S. H., Do, J. B., Ro, S. G., and Do, C. H., "Fabrication and Characteristics of Resin - Type Neutron Shielding Materials for Spent Fuel Shipping Cask", Journal of Industrial and Engineering Chemistry, Vol.7, No.3, 1996, pp.597-604.

Jun, J., Kim, J., Bae, Y., and Seo, Y. S., "Enhancement of dispersion and adhesion of B4C particles in epoxy resin using direct ultrasonic excitation", Journal of Nuclear Materials, Vol.416, 2011, pp.293-297. crossref(new window)

KS A ISO 14152, "Neutron radiation protection shielding-Design principles and considerations for the choice of appropriate materials", Korean Standards Association, 2012, p.77.


Morioka, A., Sakurai, S., Okuno, K., Sato, S., Verzirov, Y., Kaminaga, A., Nishitani, T., Tamai, H., Kudo, Y., Yoshida, S., and Matsukawa, M., "Development of 300C heat resistant boron-loaded resin for neutron shielding", Journal of Nuclear Materials, Vol.367-370, 2007, pp.1085-1089. crossref(new window)

KS L 5105, "Testing method for compressive strength of hydraulic cement mortar", Korean Standards Association, 2012, p.5.

KS L 5104, "Testing method for tensile strength of hydraulic cement mortars", Korean Standards Association, 2012, p.8.

ASTM C143, "Standard Test Method for Slump of Hydraulic- Cement Concrete", ASTM International, 2015, p.4.

Park, H., Kim, J., and Choi, K.-I., "Neutron Spectrum Measurement at the Workplace of Nuclear Power Plant with Bonner Sphere Spectrometer", Journal of Nuclear Science and Technology, Supplement 5, 2008, pp.298-301.