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

Authors

Murtafi'atin Rini
Widarto Widarto
Susilo Susilo
Made Dharma Putra Ngurah

Abstract

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.

Publication Date

4-27-2019

Recommended Citation

Rini, Murtafi'atin; Widarto, Widarto; Susilo, Susilo; and Ngurah, Made Dharma Putra (2019) "Analysis of Barite Concrete as a Potential Neutron Radiation Shielding Material for BNCT Facilities," ASEAN Journal on Science and Technology for Development: Vol. 36: No. 1, Article 3.
DOI: https://doi.org/10.29037/ajstd.528
Available at: https://ajstd.ubd.edu.bn/journal/vol36/iss1/3