A significant review on beam optimization for boron neutron capture therapy

Abstract

The thermal column at the TRIGA PUSPATI (RTP) research reactor can produce thermal neutron. However, the optimization on the thermal neutron flux produced should be performed to gain a sufficient thermal neutron for boron neutron capture therapy purpose. Thus, the objective of this review is to optimize the thermal neutron flux by designing the collimator with different materials at the thermal column. In order to fulfil the requirement, set by the IAEA standard, the study of BNCT around the world was being reviewed to study the suitable measurement, material, design, and modification for BNCT at the thermal column of TRIGA MARK-II, Malaysia. Initially, the BNCT mechanisms and history was review. Then, this paper review on the design and modifications for BNCT purpose around the world. Based on this review, suitable material and design can be used for the BNCT in Malaysia. Moreover, this paper also reviews the current status of BNCT at the RTP with the measurement of the thermal neutron flux was conducted along the thermal column at 250 kW. The thermal column of RTP was divided into 3 phases (Phase 1, Phase 2 and Phase 3) so that an accurate measurement can be obtained by using gold foil activation method. This value was used as a benchmark for the neutron flux produced from the thermal column. The collimator was designed using different types of materials, and their characteristic towards gamma and neutron flux was investigated. The reviewed demonstrated that the final thermal neutron flux produced was significantly for BNCT purpose. Lastly, this paper recommends the future research can be conducted on BNCT at RTP.

Analisis Distribusi Fluks Neutron Dan Laju Dosis Sinar Gamma Pada Kolom Termal Reaktor Kartini Untuk Boron Neutron Capture Therapy (Bnct) Dengan Software Phits

“…Pengaturan geometri dan desain fasilitas BNCT dipertimbangkan untuk mengoptimalkan fluks neutron epitermal agar berhasil digunakan sebagai balok dalam studi BNCT. Ada beberapa studi kasus yang sedang diamati di seluruh dunia untuk menemukan kelayakan dalam memodifikasi neutron epitermal di reaktor penelitian untuk BNCT (Shalbi, Sazali, & Salleh, 2020). Gambar 1(a) menunjukkan kolom termal Reaktor Kartini sebelum modifikasi.…”

The Investigation of Lead Borate Glass Composites for Boron Neutron Capture Therapy Shielding

“…The associated resultant linear energy transfer of alpha particle is significantly high, 150 KeV/micrometer, while it is for Lithium-7 a 175 KeV/micrometer. Besides, a low amount of gamma-ray released could be neglected [2][3][4].…”