Preparation method for high-density, large-size, ultra-fine-pore nuclear graphite materials for fused salt piles

A high-density, large-scale technology, which is applied in the field of preparation of high-density, large-scale, ultra-fine pore-sized nuclear graphite materials for molten salt reactors, can solve the problems of large specific surface area and surface energy of particles and inability to prepare large-scale nuclear graphite materials, etc. Achieve uniform internal temperature, eliminate intermittent, and avoid stress concentration

Active Publication Date: 2018-12-25
SINOSTEEL NEW MATERIAL ZHEJIANG
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0016] In view of this, the present invention is aimed at the deficiencies in the prior art, and its main purpose is to provide a method for preparing high-density, large-size, ultra-fine pore-diameter nuclear graphite for molten salt reactors using 1-5 μm coke aggregates, which solves the problem of The smaller the average particle size of the traditional aggregate, the larger the specific surface area and surface energy of the particles, and the technical problem that it is impossible to prepare large-size nuclear graphite materials. A variety of halogen gases are introduced as purification gases and purified synchronously during the graphitization process. The process of this method is clear. Reliable and feasible technology, suitable for mass production

Method used

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  • Preparation method for high-density, large-size, ultra-fine-pore nuclear graphite materials for fused salt piles
  • Preparation method for high-density, large-size, ultra-fine-pore nuclear graphite materials for fused salt piles
  • Preparation method for high-density, large-size, ultra-fine-pore nuclear graphite materials for fused salt piles

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0102] 1. Raw materials: 80 parts by weight of pitch coke with an average particle size of 1 μm and 20 parts by weight of pitch;

[0103] 2. Preparation method:

[0104] 1) Selection of raw materials: aggregate and binder, the fixed carbon content in the aggregate is ≥98.5%, the ash content is ≤0.5%, both boron (B) and gadolinium (Gd) are less than 0.1ppm, samarium (Sm), europium (Eu ), cadmium (Cd) and lithium (Li) are all less than 0.5ppm, moisture ≤0.5%, sulfur ≤0.1%;

[0105] The ash content in the binder is ≤0.5%, the volatile content is 35-60%, the coking value is 40-70%, the softening point is 80-200°C, the quinoline insoluble matter is 8-25%, and the toluene insoluble matter is 25- 55%;

[0106] 2) Raw material grinding: the aggregate is ground and pulverized so that the average particle size does not exceed 1 μm;

[0107] 3) Ingredients and kneading: Pour pitch coke and pitch into a kneader and knead at a temperature of 150°C for 80 minutes;

[0108] 4) Molding: P...

Embodiment 2

[0114] 1. Raw materials: 70 parts by weight of petroleum coke with an average particle size of 3 μm and 30 parts by weight of pitch;

[0115] 2. Preparation method:

[0116] 1) Selection of raw materials: aggregate and binder, the fixed carbon content in the aggregate is ≥98.5%, the ash content is ≤0.5%, both boron (B) and gadolinium (Gd) are less than 0.1ppm, samarium (Sm), europium (Eu ), cadmium (Cd) and lithium (Li) are all less than 0.5ppm, moisture ≤0.5%, sulfur ≤0.1%;

[0117] The ash content in the binder is ≤0.5%, the volatile content is 35-60%, the coking value is 40-70%, the softening point is 80-200°C, the quinoline insoluble matter is 8-25%, and the toluene insoluble matter is 25- 55%;

[0118] 2) Raw material grinding: the aggregate is ground and pulverized so that the average particle size does not exceed 3 μm;

[0119] 3) Batching and kneading: Pour pitch coke and pitch into a kneader and knead at a temperature of 300°C for 120 minutes;

[0120] 4) Molding:...

Embodiment 3

[0126] 1. Raw materials: 65 parts by weight of pitch coke with an average particle size of 5 μm and 35 parts by weight of pitch;

[0127] 2. Preparation method:

[0128] 1) Selection of raw materials: aggregate and binder, the fixed carbon content in the aggregate is ≥98.5%, the ash content is ≤0.5%, both boron (B) and gadolinium (Gd) are less than 0.1ppm, samarium (Sm), europium (Eu ), cadmium (Cd) and lithium (Li) are all less than 0.5ppm, moisture ≤0.5%, sulfur ≤0.1%;

[0129] The ash content in the binder is ≤0.5%, the volatile content is 35-60%, the coking value is 40-70%, the softening point is 80-200°C, the quinoline insoluble matter is 8-25%, and the toluene insoluble matter is 25- 55%;

[0130] 2) Raw material grinding: the aggregate is ground and pulverized so that the average particle size does not exceed 5 μm;

[0131] 3) Ingredients and kneading: Pour pitch coke and pitch into a kneader and knead at a temperature of 400°C for 150 minutes;

[0132] 4) Molding: Pu...

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Abstract

The invention provides a preparation method for high-density, large-size and ultra-fine-pore nuclear graphite materials for fused salt piles from coke aggregates 1-5 micrometers in size. The preparation method has the advantages that in the forming process, paste is compacted through vibration and ramming, calcination as well as temperature rise speeds and in-furnace temperature differences in thegraphitization process are controlled, and the shrinkage rate of graphite green bodies is further controlled, so that the technical problems that the smaller the average particle size of conventionalaggregates is, the larger the specific surface area and the surface energy of particles are, and the large-size nuclear graphite materials cannot be prepared are solved; multiple halogen gases are introduced as purification gases, and simultaneous purification in the graphitization process is realized; the method is clear in procedure, technically reliable and feasible, and suitable for large-scale production.

Description

technical field [0001] The invention relates to a technology in the field of nuclear graphite production, in particular to a method for preparing a nuclear graphite material with high density and large size and ultrafine aperture for molten salt reactors. Background technique [0002] Graphite is used in thermal neutron reactors, and is also expected to be used in fusion reactors. In thermal neutron reactors, it can be used as a neutron moderator in the fuel zone, a reflector material around the fuel zone, and a structural material inside the core. [0003] Nuclear graphite is a graphite material used in the nuclear industry. [0004] Molten salt reactor is one of the six candidates for the fourth-generation advanced nuclear energy system, which has the characteristics of high inherent safety, less nuclear waste, non-proliferation performance and good economy. Nuclear graphite is used as the core component in the molten salt reactor, mainly for the following reasons: (1) It...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C04B35/532C04B35/622
CPCC04B35/521C04B35/522C04B35/532C04B35/622C04B2235/608C04B2235/6562C04B2235/6586C04B2235/77C04B2235/96C04B2235/9607
Inventor 黄岱杨辉李贺曹曙林
Owner SINOSTEEL NEW MATERIAL ZHEJIANG
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