High-flux neutron channel

A high-flux, neutron technology, applied in neutron sources, radiation/particle processing, nuclear power generation, etc., can solve the problems that are not conducive to the safe use of neutron sources and the personal safety of operators cannot be optimally guaranteed. , to achieve personal safety protection, reduce radiation, and reduce operating time

Inactive Publication Date: 2015-06-03
SOUTHWEAT UNIV OF SCI & TECH
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Problems solved by technology

This will not be conducive to the safe use of neutron sources, and

Method used

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  • High-flux neutron channel

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Embodiment Construction

[0021] A high-flux neutron channel, such as Figure 1-Figure 6 As shown, it is composed of neutron channel, polyethylene moderator layer, graphite reflector layer and concrete shield layer.

[0022] Neutron channel: that is, the outlet of the neutron channel, which is divided into an upper bottom surface and a lower bottom surface. The neutron channel is set in the shape of a truncated cone, and the diameter of the upper bottom surface is 8.5cm, which remains unchanged. The diameter of the lower bottom surface is larger than that of the upper bottom surface. The busbar of the neutron channel is the waistline of the right-angled trapezoid at each position on the side, the axis of the neutron channel is the line connecting the centers of the upper and lower bottom surfaces of the neutron channel, and the angle between the bus bar of the neutron channel and the axis is 3 -9 degrees, the neutron channel is 20cm long, and the interior is a vacuum; the axis of the neutron channel is...

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Abstract

The invention discloses a high-flux neutron channel. Under same conditions, more neutrons can be led out of an outlet of the neutron channel, an existing neutron channel is changed from cylinder-shaped to truncated cone-shaped, and a polyethylene slowing-down layer and a graphite reflection layer are added around the neutron channel, so that the neutron flux of the outlet of the neutron channel is increased by over 80%. Graphite is added as the reflection layer firstly, so that the neutron flux is increased by more than 50%; then, the neutron channel is changed from cylinder-shaped to truncated cone-shaped, so that the neutron flux is increased by about 60%; the polyethylene slowing-down layer is added between the neutron channel and the graphite reflection layer, so that neutrons are slowed down firstly and then the neutron flux is increased by more than 80% finally; therefore, 252 Cf neutron sources which are same in activity can lead out more neutrons of the neutron channel in the practical application aspects of neutron activation analysis and irradiation and the like, so that the economic benefits of the neutron sources are improved, the operation time of operators is shortened, and the radiation of the neutron sources to the human body and the environment can be alleviated.

Description

technical field [0001] The invention relates to a channel for increasing neutron flux by using multiple materials and a multi-layer structure, which is used for neutron activation analysis and neutron photography, belongs to the application of nuclear technology, and specifically belongs to the field of a high-flux neutron channel. Background technique [0002] 252 The Cf neutron source is a common neutron source in the experiment, which belongs to the neutron source of spontaneous fission, and its energy spectrum is relatively close to the pure fission energy spectrum. Currently, 252 The devices of Cf neutron sources in practical applications such as neutron photography, neutron activation analysis, neutron moisture measurement, industrial flaw detection, and agricultural breeding are mostly concrete structures with cylindrical channels. Although such a channel and structure can shield neutrons, the neutron flux at the outlet of the channel is relatively low. The utiliza...

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Application Information

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IPC IPC(8): G21C11/06
CPCG21G4/02G21H5/00G21K1/067Y02E30/30
Inventor 王烈林谢华付君曹巍黄祥祥
Owner SOUTHWEAT UNIV OF SCI & TECH
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