CaO-MgO-Al2O3-SiO2 glass encapsulating method for SiCf/SiC nuclear cladding tube port

A cao-mgo-al2o3-sio2, glass encapsulation technology, used in nuclear power generation, climate sustainability, fuel elements, etc., can solve the problem of difficult to meet the SiC core cladding tube packaging requirements, high connection temperature, unable to meet the cladding requirements The air-tightness requirements of the tube can achieve the effect of reducing internal residual stress, preventing interface cracking, and reducing the decay rate of nuclear radiation.

Active Publication Date: 2019-02-15
NORTHWESTERN POLYTECHNICAL UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The above methods can meet the structural requirements of the connection, but the former two have obvious cracks at the connection interface after irradiation, which cannot meet the airtightness requirements of the cladding tube, and the connection temperature of the latter is as hi...

Method used

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  • CaO-MgO-Al2O3-SiO2 glass encapsulating method for SiCf/SiC nuclear cladding tube port
  • CaO-MgO-Al2O3-SiO2 glass encapsulating method for SiCf/SiC nuclear cladding tube port
  • CaO-MgO-Al2O3-SiO2 glass encapsulating method for SiCf/SiC nuclear cladding tube port

Examples

Experimental program
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Effect test

Embodiment 1

[0034] Using CaO, MgO, Al with scale ~1μm 2 O 3 , SiO 2 Four kinds of powder, the proportion of which is: 10.5wt.%CaO, 10.5wt.%MgO, 15wt.%Al 2 O 3 ,64wt.%SiO 2 , the four powders were mixed with alcohol and ball-milled for 12 hours. After mixing, the slurry was dried to make a mixed powder. The prepared mixed powder was placed in an alumina crucible, kept at 1600° C. for 2 hours in an air atmosphere, taken out and quenched in cold water to form a transparent glass block. The glass block was ball-milled in a ball-milling jar for 10 hours and passed through a 150-mesh sieve to prepare glass powder. The prepared glass powder is mixed with alcohol to form an encapsulant, wherein the mass fraction of alcohol added is 70%. The prepared encapsulant is evenly brushed on the processed SiC f / SiC plug to be encapsulated surface, and with SiC f / SiC core cladding tube is assembled, and placed in a vacuum furnace for heat treatment. The heat treatment atmosphere is vacuum, the...

Embodiment 2

[0036] Using CaO, MgO, Al with scale ~1μm 2 O 3 , SiO 2 Four kinds of powder, the proportion by mass is: 11wt.%CaO, 9wt.%MgO, 20wt.%Al 2 O 3 ,60wt.%SiO 2, the four powders were mixed with alcohol and ball milled for 12 hours, and the slurry was dried after mixing to make a mixed powder. The prepared mixed powder was placed in an alumina crucible, held in an air atmosphere at 1600°C for 2 hours, then taken out and quenched in cold water to form a transparent glass block. The glass block was milled for 10 h in a ball mill and passed through a 150-mesh sieve to prepare glass powder. The prepared glass powder is mixed with alcohol to form an encapsulant, wherein the mass fraction of alcohol added is 70%. Apply the prepared encapsulant evenly on the processed SiC f / SiC plug to be encapsulated surface, and with SiC f The / SiC core cladding tube is assembled and placed in a vacuum furnace for heat treatment. The heat treatment atmosphere is vacuum, the heat treatment te...

Embodiment 3

[0038] CaO, MgO, Al with scale ~1μm 2 o 3 , SiO 2 The mass ratio of four kinds of powders is: 11wt.% CaO, 9wt.% MgO, 20wt.% Al 2 o 3 ,60wt.%SiO 2 , the four powders were mixed with alcohol and ball milled for 10 hours, and the slurry was dried after mixing to make a mixed powder. The prepared mixed powder was placed in an alumina crucible, held in an air atmosphere at 1650°C for 2 hours, then taken out and quenched in cold water to form a transparent glass block. The glass block was milled for 10 h in a ball mill and passed through a 150-mesh sieve to prepare glass powder. The prepared glass powder is mixed with alcohol to form an encapsulant, wherein the mass fraction of alcohol added is 90%. Apply the prepared encapsulant evenly on the processed SiC f / SiC plug to be encapsulated surface, and with SiC f The / SiC core cladding tube is assembled and placed in a vacuum furnace for heat treatment. The heat treatment atmosphere is vacuum, the heat treatment temperatu...

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Abstract

The invention relates to a CaO-MgO-Al2O3-SiO2 glass encapsulating method for a SiCf/SiC nuclear cladding tube port, wherein part of the raw materials being low in reaction activity and nuclear radiation decay rate and having no side effect on the process of the nuclear reaction is chosen, the raw material is prepared into a glass brazing filler metal through a melting-water cooling method, and a SiCf/SiC composite nuclear cladding tube is encapsulated/connected under the non-pressure condition at the applicable temperature (less than or equal to 1450 DEG C) of the domestic three-generation SiCfiber by depending on the fluidity of the glass and the wetting of a SiCf/SiC composite. The CaO-MgO-Al2O3-SiO2 glass encapsulating method has the beneficial effects that: the raw material of an encapsulating/connecting agent adopts a low-activity element, the nuclear radiation decay rate of the raw material is low, the raw material has no side effects on the process of the nuclear reaction, andthe severe nuclear environment is met. A piece of CMAS (Ca-Mg-Al-Silicate) glass is used as the encapsulating/connecting agent, the coefficient of thermal expansion is matched with that of SiC/SiC, and the interface crack caused by thermal mismatch is effectively prevented and the internal residual stress is reduced. In addition, the encapsulating/connecting condition meets the requirement of thedomestic SiCf/SiC composite.

Description

technical field [0001] The invention belongs to the preparation technology of glass encapsulation, and relates to a kind of SiC f / SiC core cladding tube port packaging and connection technology, specifically involving SiC f / SiC core-clad tube port CaO-MgO-Al 2 O 3 -SiO 2 The glass encapsulation method is mainly used in the encapsulation and connection at the joint of the cladding tube. Background technique [0002] The main reasons for the Fukushima nuclear accident in Japan: the failure of the reactor cooling system led to a rapid increase in the core temperature; the zirconium cladding tube gradually lost its mechanical properties above 600 ℃ and was damaged, causing the core to be exposed, collapsed and melted; at 1000 ℃, The violent reaction between zirconium and water releases a large amount of hydrogen, which causes an explosion and leads to a nuclear leak. [0003] After the Fukushima accident, the research and development have radiation resistance, high tempe...

Claims

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Application Information

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IPC IPC(8): C04B37/00C03C8/24G21C3/10
CPCC03C8/24C04B37/003C04B2237/10G21C3/10Y02E30/30
Inventor 范尚武马旭姬彪张立同成来飞李晓强
Owner NORTHWESTERN POLYTECHNICAL UNIV
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