Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities

Rini Murtafi'atin (Department of Physics, Mathematics and Science Faculty, Semarang State University, Semarang 50229, Indonesia)
Widarto Widarto (Center of Accelerator Science and Technology, National Nuclear Energy Agency, Yogyakarta 55281, Indonesia)
Susilo Susilo (Department of Physics, Mathematics and Science Faculty, Semarang State University, Semarang 50229, Indonesia)
Ngurah Made Dharma Putra (Department of Physics, Mathematics and Science Faculty, Semarang State University, Semarang 50229, Indonesia)

ASEAN Journal on Science and Technology for Development
Vol. 36 No. 1 (2019): Vol 36 No 1 (2019)

This research aimed to determine the potential of barite concrete as a neutron radiation shielding material in the development of boron neutron capture therapy, by obtaining its neutron attenuation coefficient. Barite concrete samples were supplied by the Center of Accelerator Science and Technology in Yogyakarta, Indonesia. The experiment consisted of two parts, namely density analysis and determination of the neutron attenuation coefficient. For the latter, plutonium-beryllium was used as the neutron source, while a high purity germanium detector was used to measure the neutron radiation level. The results showed that barite concrete with a 2130 kg.m–3 density had a neutron attenuation coefficient of 0.0871 cm–3.