Measurement of neutron flux at thermal column using gold foil activation analysis and TLD detector: technical review

• Main Authors: Safwan, Shalbi, Norazlianie, Sazali, Wan Norharyati, Wan Salleh
• Format: Article
• Language: English
• Published: Akademi Baru 2021
• Subjects: TA Engineering (General). Civil engineering (General); TJ Mechanical engineering and machinery
• Online Access: http://umpir.ump.edu.my/id/eprint/35217/1/2-Shalbi%2C%20S.%2C%20Sazali%2C%20N.%2C%20%26%20Salleh%2C%20W.%20N.%20W.%20%282021%2918220-1-10-20210606.pdf; http://umpir.ump.edu.my/id/eprint/35217/; https://doi.org/10.37934/arfmts.83.2.2543; https://doi.org/10.37934/arfmts.83.2.2543

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 Boron Neutron Capture Therapy (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 reviewed demonstrated that the final thermal neutron flux produced was significantly for BNCT purpose