Verification of the Thermal Neutron Shielding Effect of the Shielding Door of the LHD Experimental Hall

The energy dependence of gamma-ray sensitivity of a neutron imaging plate (NIP) has been measured. The gamma-ray sensitivity is equivalent to one half that of a thermal neutron at a gamma-ray energy less than 300 keV, and 1/40 at greater than 300 keV. The shielding of the NIP, by lead, from gamma rays in the experimental hall of the reactor JRR-3M of the Japan Atomic Energy Research Institute (JAERI) was measured. It was found that lead of thickness 40 mm is sufficient to reduce the gamma-ray background to 1/10 on a normalized scale. Covering the NIP with lead foil of thickness 1 mm results in a decrease of the gamma-ray background without reduction of the neutron signal.

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Thermal neutron flux measurements in the STAR experimental hall

Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment ◽

10.1016/j.nima.2014.04.035 ◽

2014 ◽

Vol 756 ◽

pp. 68-72 ◽

Cited By ~ 5

Author(s):

Yuri Fisyak ◽

Oleg Tsai ◽

Flemming Videbæk ◽

Zhangbu Xu

Keyword(s):

Neutron Flux ◽

Thermal Neutron ◽

Thermal Neutron Flux ◽

Experimental Hall ◽

Flux Measurements

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Mechanical properties and thermal neutron shielding efficiency of high B amorphous ribbons in the Fe-B-Mo-Cr system

Metals and Materials International ◽

10.1007/s12540-016-6106-6 ◽

2016 ◽

Vol 22 (5) ◽

pp. 825-830 ◽

Cited By ~ 4

Author(s):

Jaewon Moon ◽

Seonghoon Yi

Keyword(s):

Mechanical Properties ◽

Thermal Neutron ◽

Neutron Shielding ◽

Amorphous Ribbons ◽

Cr System

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Research on Thermal Neutron Shielding Performance of TiB2-Al Composite Materials

10.26434/chemrxiv.13611725.v1 ◽

2021 ◽

Author(s):

Chao Wang ◽

Zhefu Li ◽

Mengge Dong ◽

Lu Zhang ◽

Jianxing Liu ◽

...

Keyword(s):

Thermal Neutron ◽

Cross Section ◽

Neutron Fluence ◽

Thermal Neutrons ◽

Neutron Shielding ◽

Preparation Methods ◽

Neutron Fluence Rate ◽

Maximum Value ◽

Al Composite ◽

Macroscopic Cross Section

Although the various excellent properties and preparation methods of TiB2-based composites have been extensively studied, their neutron shielding properties have not received as much attention. In this article, the neutron shielding performance of the previously prepared TiB2-Al composite will be studied. The photo neutron source device was used to carry out neutron irradiation tests on test samples with a thickness of 10 mm. The average thermal neutron shielding rate of TiB2-based boron-containing composites is 17.55%, and the shielding rate increases with the increase of BN content. The macroscopic cross-section of thermal neutrons of the composites generally shows a stable trend, and when the BN content is 10%, the thermal neutrons macroscopic cross section reaches the maximum value of 7.58cm-1. With the increase of the BN content, the thermal neutron fluence rate shows a gradually decreasing trend.

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