Optimization and designing collimator for boron neutron capture therapy at the thermal column of RTP

Shalbi, Safwan; Salleh, Wan Norharyati Wan; Rosdi, Muhammad Aliff Ashraff; Idris, Faridah Mohamad

doi:10.1088/1757-899x/555/1/012017

Cited by 4 publications

(1 citation statement)

References 4 publications

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“…The properties of graphite that have higher thermal conductivity have increased the measurement of thermal and epithermal neutron flux at Phase 1 [49]. Across the beam line, the thermal neutron flux was higher than epithermal neutron flux with 1.00 x 10 2 neutron.cm -2 s -1 difference because the thermal column itself produce are well known as the thermal neutron source at the RTP [50]. The aim of this measurement to clearly see the thermal and epithermal neutron across the beam line for the optimization purpose for the collimator [3].…”

Section: Tablementioning

confidence: 99%

Measurement of Neutron Flux at Thermal Column Using Gold Foil Activation Analysis and TLD Detector: Technical Review

Shalbi

Sazali

Salleh

2021

ARFMTS

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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.

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Section: Tablementioning

confidence: 99%

Measurement of Neutron Flux at Thermal Column Using Gold Foil Activation Analysis and TLD Detector: Technical Review

Shalbi

Sazali

Salleh

2021

ARFMTS

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Neutronic analysis of DECY-13 cyclotron target system as a neutron source for SAMOP

Isdandy

Syarip

Silakhuddin

et al. 2020

J. Phys.: Conf. Ser.

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The Centre for Accelerator Science and Technology (PSTA) has developed a subcritical reactor for the molybdenum-99 (99Mo) production (SAMOP). This device requires an external neutron source. For experimental purposes, SAMOP is still driven by an external neutron source from a critical reactor, i.e. from the radial beam-port of the Kartini reactor. PSTA is also developing a 13 MeV cyclotron (DECY-13) for the production of fluorine-18 (18F) which can generate neutron as by-products. This cyclotron has an opportunity to be used as an external neutron source for the SAMOP. In this work, particle transport simulations have been carried out to determine the characteristics of the neutron produced by the DECY-13. The simulation results show that DECY-13 produces an average neutron flux of 2.6347 × 109 particles/cm2s and around 97% of them are the fast neutron. Based on the analysis, it concluded that the DECY 13 could be used as an external neutron source for the SAMOP by the addition of a neutron collimator.

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A significant review on beam optimization for boron neutron capture therapy

Shalbi

Sazali

Salleh

2020

IOP Conf. Ser.: Mater. Sci. Eng.

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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.

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Optimization and designing collimator for boron neutron capture therapy at the thermal column of RTP

Cited by 4 publications

References 4 publications

Measurement of Neutron Flux at Thermal Column Using Gold Foil Activation Analysis and TLD Detector: Technical Review

Measurement of Neutron Flux at Thermal Column Using Gold Foil Activation Analysis and TLD Detector: Technical Review

Neutronic analysis of DECY-13 cyclotron target system as a neutron source for SAMOP

A significant review on beam optimization for boron neutron capture therapy

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