Evaluation of the calibration factors of neutron dose rate meters in a 241Am–Be neutron field

Le, Ngoc-Thiem; Hoang, Sy Minh Tuan; Nguyen, Quynh Ngoc; Tran, Hoai-Nam

doi:10.1007/s41365-019-0654-7

Cited by 4 publications

(2 citation statements)

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“…The neutron ambient dose equivalent (rate) meter is often used to measure the ambient dose equivalent produced by neutron radiation. Both neutrons that arrive directly from the source to the meter and neutrons scattered from the air, concrete walls, and other objects in the calibration room contribute to the measurement results [20]. A BH3105 type neutron ambient dose equivalent (rate) meter made in China was used to measure the dose equivalent behind the material samples in this experiment.…”

Section: Neutron Experiments Layoutmentioning

confidence: 99%

“…(b) The layout was Source Target + Shadow Cone + detector: the shadow cone completely blocked the direct neutrons. At this time, the dose equivalent caused by the scattered neutrons was measured [20]. Combined with the results of step (a), the dose equivalent caused by direct neutrons reaching the detector without sample material could be obtained, D 0 ;…”

Section: Neutron Experiments Layoutmentioning

confidence: 99%

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Study on a High-Boron-Content Stainless Steel Composite for Nuclear Radiation

Sun

et al. 2021

Materials

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In this research, a high-boron-content composite material with both neutron and γ rays shielding properties was developed by an optimized design and manufacture. It consists of 304 stainless steel as the matrix and spherical boron carbide (B4C) particles as the functional particles. The content of B4C is 24.68 wt%, and the particles’ radius is 1.53 mm. The density of the newly designed material is 5.17 g·cm−3, about 68.02% of that of traditional borated stainless steel containing 1.7 wt% boron, while its neutrons shielding performance is much better. Firstly, focusing on shielding properties and material density, the content and the size of B4C were optimized by the Genetic Algorithm (GA) program combined with the MCNP program. Then, some samples of the material were manufactured by the infiltration casting technique according to the optimized results. The actual density of the samples was 5.21 g cm−3. In addition, the neutron and γ rays shielding performance of the samples and borated stainless steel containing 1.7 wt% boron was tested by using an 241Am–Be neutron source and 60Co and 137Cs γ rays sources, respectively, and the results were compared. It can be concluded that the new designed material could be used as a material for nuclear power plants or spent-fuel storage and transportation containers with high requirements for mobility.

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Section: Neutron Experiments Layoutmentioning

confidence: 99%

Section: Neutron Experiments Layoutmentioning

confidence: 99%