Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor

Albarqi, Mubarak; Alsulami, Raed; Akyurek, T.; Graham, Joseph

doi:10.1007/s10967-019-06561-2

Cited by 6 publications

(3 citation statements)

References 20 publications

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“…The neutron flux measurement is determined by using gold foil activation method that utilizes 197 Au with neutrons to produce 198 Au [25]. In this experiment, there are two types of samples being prepared which is pure 99.99% gold foil and Cadmium (Cd).…”

Section: Neutron Measurement 221 Gold Foil Activation Methodsmentioning

confidence: 99%

“…In this experiment, there are two types of samples being prepared which is pure 99.99% gold foil and Cadmium (Cd). The gold foil is used in this experiment because the gold foil will decay and emitting single gamma of well-known energy and the half-life of 2.81 days of gold is suitable for experimental purposes [25]. The cadmium well known as the thermal neutron filter will be used to cover gold foil for aiming separate the thermal and epithermal neutron flux.…”

Section: Neutron Measurement 221 Gold Foil Activation Methodsmentioning

confidence: 99%

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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: Neutron Measurement 221 Gold Foil Activation Methodsmentioning

confidence: 99%

Section: Neutron Measurement 221 Gold Foil Activation Methodsmentioning

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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“…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 reflector analysis for the beam-port of the Missouri S&T Reactor

Akyurek

Vaz

Alajo

et al. 2019

J Radioanal Nucl Chem

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Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor

Cited by 6 publications

References 20 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

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

Neutron reflector analysis for the beam-port of the Missouri S&T Reactor

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