Neutron and gamma ray fluences measurement at radial Beam Port 1 of TRIGA MARK II PUSPATI research reactor

Rosdi, Muhammad Aliff Ashraff; Goh, Pei Sean; Idris, Faridah Mohamad; Shalbi, Safwan; Sarkawi, Muhammad Syahir; Ali, Nur Syazwani Mohd; Jamsari, Nur Liyana; Ramli, Ahmad Syafiq; Azman, Azraf

doi:10.1088/1757-899x/298/1/012033

Cited by 6 publications

(4 citation statements)

References 6 publications

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“…Technically, the epithermal neutron shows the gradually decline of flux along Phase 2 and Phase 3 without any fluctuation and follow the standard law of radiation and distance [3]. Both neutron thermal and epithermal neutrons flux decrease with the distance from 142 cm to 283.9 cm from graphite thermal column as the flux generally is exponentially decreasing with distance [48]. Based on Figure 7, from the Phase 1 to the Phase 2, the thermal and epithermal neutron flux is significantly reduced about 99.8% for thermal neutron flux and 96.5% for epithermal neutron flux.…”

Section: Tablementioning

confidence: 80%

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: 80%

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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“…As shown in Equation (1), the radiation energy transmitted through the shielding sheet can be expressed as a product of the incident radiation fluence and dose function R (

) [ 24 ]. The radiation fluence is included owing to the interaction with the material when radiation penetrates the shielding sheet [ 25 ].

…”

Section: Methodsmentioning

confidence: 99%

Metal Particle Pencil Beam Spray-Coating Method for High-Density Polymer–Resin Composites: Evaluation of Radiation-Shielding Sheet Properties

Kim

2023

Materials

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Medical shielding suits must be lightweight and satisfy the requirements of thin films to guarantee user mobility and safety. The thin film weight is related to the density and thickness, which are associated with the particle dispersion in shielding materials. An even distribution of metal particles in a polymer can maintain the spacing among them. This paper proposes a pencil beam spray-coating method that involves spraying a constant amount of a polyethylene and tungsten mixture in a thin beam onto a nonwoven fabric at a constant speed. This technique yields higher productivity than does the electrospinning method and is expected to produce materials with better shielding performance than that of materials obtained using the calender method. The shielding performance was evaluated by manufacturing shielding sheets (thickness: 0.48–0.54 mm) using the calender and pencil beam spray-coating methods under the same conditions. The densities and performances of the sheets differed significantly. The sheet manufactured using the proposed method had an even particle dispersion and exhibited 2–4% better shielding performance than did that manufactured using the calender method. Therefore, the pencil beam spray-coating method can effectively satisfy the requirements of thin films for medical radiation-shielding materials while increasing the material flexibility.

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“…The reactivity of the reactor is controlled by five fuel follower and one air follower control rods which contain Boron Carbide (B 4 C) as the neutron absorber material. The central neutron flux is suppressed by eighteen graphite dummy elements located around the center (13) and near the periphery (5). In order to support its research and  Corresponding author.…”

Section: Baecmentioning

confidence: 99%

“…at two irradiation facilities of the TRIGA Mark II reactor at ENEA Casaccia Research Center, Italy, for radiation damage tests [4]. Presently, a day neutron activation technique is widely used for measuring neutron and gamma photonic flux at the beam ports of the TRIGA research reactor [5][6][7]. The aim of this study is not only to calculate the flux at the beam ports with probabilistic approach but also to discover a more optimum TRIGA core configuration for better irradiation system than the existing core.…”

Section: Baecmentioning

confidence: 99%

Optimizing Neutronic and Photonic Performance in Irradiation Systems of Symmetric TRIGA Cores

Shauddin

2023

Atom Indo.

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The BAEC TRIGA MARK-II Research Reactor (BTRR) in Bangladesh has been used for a wide range of purposes, including basic and applied nuclear research and human resource development. Therefore, its core management should be flexible to meet various objectives with different priorities and to deliver the best possible outcome. In this study, neutron and gamma photon flux variation was studied at different radial and axial irradiation systems of the current core (C-0) as well as six symmetric reconfigurations (C-1, C-2, C-3, C-4, C-5, and C-6) of the existing BTRR using the universal MCNP code. While keeping the exact core component and material density, the symmetric reconfigured cores were modeled based on core criticality calculation and excess reactivity in the critical state. Finally, it was observed that the reconfigured core C-1 has the best neutronic and photonic performance at the irradiation systems compared to other reconfigured cores, against the reference core C-0.

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Neutron and gamma ray fluences measurement at radial Beam Port 1 of TRIGA MARK II PUSPATI research reactor

Cited by 6 publications

References 6 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

Metal Particle Pencil Beam Spray-Coating Method for High-Density Polymer–Resin Composites: Evaluation of Radiation-Shielding Sheet Properties

Optimizing Neutronic and Photonic Performance in Irradiation Systems of Symmetric TRIGA Cores

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