Development of advanced shield systems for fast neutrons

Tinashe Dhliwayo


Neutron shielding capabilities of different materials were investigated using Monte Carlo method. MCNP5 was used to evaluate the capability of some hydrogen rich materials as possible neutron shields. Materials like magnesium borohydride (Mg (BH4)2), beryllium borohydride   (Be (BH4)2) and zirconium hydride (ZrH2) were compared with conventional neutron shielding materials such as water and polythene. Their richness in hydrogen makes them effective neutron shields. A combination of hydrogen rich materials and high-Z atoms improves the fast neutron shielding capabilities of both conventional materials and hydrogen rich materials. Also, the thickness of hydrogen rich materials can be reduced by combining with steels without compromise to their shielding capabilities.


Borohydride, Mg (BH4)2, (Be (BH4)2), metal hydride, ZrH2, HT-9 steel, boron stainless steel, MCNP5, radiation shielding


Elbio Calzada et al (2011). Reusable shielding material for neutron and gamma radiation.

Nuclear Instruments and Methods in Physics Research A 651 (2011) 77-80

Akkurt et al (2010). Radiation shielding of concrete containing zeolite. Radiation

Measurements 45 (2010) 827-830

Atsuhiko M. Sukegawa et al (2011). Flexible heat resistant neutron shield resin. Journal of

Nuclear materials 417 (2011), 850-853

Gary. S. Was (2007). Fundamentals of Radiation Materials Science. Springer-Verlag Berlin

T Hayashi et al (2009). Advanced neutron shielding material using zirconium borohydride

and zirconium hydride. Journal of Nuclear materials 386-388 (2009) 119-121

T Hayashi et al (2005). Neutronics assessment of advanced shield materials using metal

hydride and borohydride for fusion reactors. Fusion Engineering and Design 81 (2006)


Louis Schlapbach and Seijirau Suda (2011). Advanced Materials for Energy Conversion III.


Hai Wen Li et al. Recent Progress in Metal Borohydrides for Hydrogen Storage. Energies


S. K Sahoo et al (2012). Annealing Behaviour of Ferritic HT-9 Steel. Materials Science

Forum 702-703 (2012) 794-797

X-5 Monte Carlo Team, “MCNP-A general Monte Carlo N-Particle Transport Code Version

– Volume 1,” April 2003.

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