Measurement of Neutron Flux Spectra by a Multiple Foil Activation Iterative Method and Comparison with Reactor Physics Calculations and Spectrometer Measurements

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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Determination of the Thermal Neutron Flux by Measuring Gamma Radiations with High and Low Resolution Detectors

Journal of Nuclear Physics Material Sciences Radiation and Applications ◽

10.15415/jnp.2019.62027 ◽

2019 ◽

Vol 6 (2) ◽

pp. 187-193

Author(s):

M. M. Hosamani ◽

A. S. Bennal ◽

N. M. Badiger

Keyword(s):

Neutron Flux ◽

Thermal Neutron ◽

Thermal Neutron Flux ◽

High Energy ◽

High Energy Resolution ◽

Indium Foil ◽

Hpge Detectors ◽

Foil Activation ◽

Gamma Radiations

Thermal neutron flux (Фth) of Americium-Beryllium (Am-Be) neutron source has been measured by adopting the foil activation method. The neutrons emitted from Am-Be source are used to activate the indium-115 (115In) foil. The gamma radiations emitted from the activated isomer 116m1In are measured with NaI(Tl) and HPGe detectors. The thermal neutron flux is measured by adopting the cadmium (Cd) foil difference technique in which the Cd foil placed in front of the source to prevent the thermal neutrons from entering into the indium foil. The neutron flux is determined by measuring the gamma radiation emitted from indium foil using a low and high energy resolution NaI(Tl) and HPGe detectors respectively. The measured thermal neutron flux obtained from both detectors has been compared and found that the Фth does not depend on the resolution and type of the detectors used in the present investigations.

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Neutron-Flux Spectral Determination by Foil Activation

Nuclear Science and Engineering ◽

10.13182/nse86-a17618 ◽

1967 ◽

Vol 27 (3) ◽

pp. 533-541 ◽

Cited By ~ 43

Author(s):

W. N. McElroy ◽

S. Berg ◽

G. Gigas

Keyword(s):

Neutron Flux ◽

Spectral Determination ◽

Foil Activation

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Neutron Spectrum

Accelerator-Driven System at Kyoto University Critical Assembly ◽

10.1007/978-981-16-0344-0_5 ◽

2021 ◽

pp. 125-156

Author(s):

Cheol Ho Pyeon

Keyword(s):

Neutron Spectrum ◽

High Energy ◽

Reactor Physics ◽

The Core ◽

Foil Activation ◽

Fission Neutrons ◽

Spallation Neutrons ◽

Core Characteristics ◽

Mev Protons ◽

Fast Neutron Spectrum

AbstractThe subcritical multiplication factor is considered an important index for recognizing, in the core, the number of fission neutrons induced by an external neutron source. In this study, the influences of different external neutron sources on core characteristics are carefully monitored. Here, the high-energy neutrons generated by the neutron yield at the location of the target are attained by the injection of 100 MeV protons onto these targets. In actual ADS cores, liquid Pb–Bi has been selected as a material for the target that generates spallation neutrons and for the coolant in fast neutron spectrum cores. The neutron spectrum information is acquired by the foil activation method in the 235U-fueled and Pb–Bi-zoned fuel region of the core, modeling the Pb–Bi coolant core locally around the central region. The neutron spectrum is considered an important parameter for recognizing information on neutron energy at the target. Also, the neutron spectrum evaluated by reliable methodologies could contribute to the accurate prediction of reactor physics parameters in the core through numerical simulations of desired precision. In the present chapter, experimental analyses of high-energy neutrons over 20 MeV are conducted after adequate preparation of experimental settings.

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