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High-temperature and high-radiation inorganic shielding material

A technology of shielding material and inorganic cementitious material, applied in the field of high temperature resistant and radiation resistant inorganic shielding materials, can solve the problems of loss of strength, molecular chain breakage, mechanical strength drop, etc. The effect of efficiency

Pending Publication Date: 2017-11-10
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

As the service time increases, the polymer material will continue to decompose, the molecular chain will break, the mechanical strength will decrease, and eventually it will lose its strength and cannot be used
At present, the shielding design of marine reactors puts forward higher requirements on the operating temperature of neutron shielding materials. For example, the operating temperature of the first layer of neutron shielding materials behind the metal insulation layer of the reactor is as high as 200°C, and no materials are currently available.

Method used

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  • High-temperature and high-radiation inorganic shielding material

Examples

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Embodiment 1

[0037] A high temperature and radiation resistant inorganic shielding material comprises 10 parts of aluminate cement and 90 parts of aluminum hydroxide powder.

Embodiment 2

[0039] A high temperature and radiation resistant inorganic shielding material comprises 10 parts of aluminate cement, 80 parts of aluminum hydroxide powder and 10 parts of boron glass.

Embodiment 3

[0041] A high temperature and radiation resistant inorganic shielding material, comprising 20 parts of aluminate cement, 70 parts of aluminum hydroxide powder, 1 part of water reducing agent and 9 parts of boron carbide.

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PUM

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Abstract

The invention provides a high-temperature and high-radiation inorganic shielding material. The high-temperature and high-radiation inorganic shielding material comprises an inorganic gelling material and a shielding function component, and the shielding function component is any one of or the combination of two or more of hydroxide, a neutron absorption component, a gamma ray shielding component and the like. According to the high-temperature and high-radiation inorganic shielding material, the inorganic gelling material, hydroxide and the neutron absorption component are used as main components, the long-term using temperature can reach 230 DEG C, the shielding material has high shielding efficiency on fast neutrons, intermediate neutrons and thermal neutrons, increases the using temperature of neutron shielding materials, is a powerful supplement for the types of the neutron shielding materials, improves the flexibility of reactor shielding system design, and solves the radiation aging and thermal aging problem faced by traditional organic shielding materials in service and the problem that no neutron shielding material is available under a high temperature environment.

Description

technical field [0001] The invention belongs to the technical field of radiation protection and nuclear safety, and is applied to the protection field of isotope neutron sources, nuclear reactors and other neutron radiation sources or neutron-gamma composite radiation sources, and specifically refers to a high-temperature-resistant and radiation-resistant inorganic shielding material. Background technique [0002] Both the isotope neutron source and the reactor will release neutron rays during the use process. The protection of neutron rays is generally shielded by materials with high hydrogen content and large neutron absorption cross-section. The commonly used neutron shielding materials are polyethylene, boron polystyrene, etc. Ethylene, lead boron polyethylene, concrete materials, boron aluminum, boron steel, etc. Polyethylene, boron polyethylene, and lead-boron polyethylene have high hydrogen content and good neutron shielding effect, but their softening temperature is ...

Claims

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Application Information

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IPC IPC(8): G21F1/02G21F1/04
CPCG21F1/02G21F1/047
Inventor 李圆圆李统业潘小强杨静吴莹张良
Owner NUCLEAR POWER INSTITUTE OF CHINA
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