sic f /sic nuclear cladding tube port cao-y 2 o 3 -al 2 o 3 -sio 2 Glass encapsulation method

Abstract

The present invention relates to a SiC f / SiC Core Cladding Tube Port CaO‑Y 2 o 3 ‑Al 2 o 3 ‑SiO2 2 In the glass encapsulation method, the present invention selects some raw materials with low reactivity, small decay rate of nuclear radiation, and no side effects on the nuclear reaction process, and prepares them into glass solder by melting-water cooling method, relying on its combination with SiC f / SiC matching thermal expansion coefficient, better wettability and low high-temperature viscosity, realize SiC under the applicable temperature of domestic third-generation SiC fiber (≤1450°C) and under pressure-free conditions f / Encapsulation / joining of SiC composite core cladding tubes. Advancing SiC f / SiC nuclear cladding tubes are applied to nuclear reactors to prevent nuclear radiation leakage accidents and improve the safety of nuclear reactor operations. The beneficial effect is: the raw materials selected for the encapsulant are all low-activity elements, the decay of nuclear radiation is small, and there is no side effect on the nuclear reaction process, and the mechanical and airtight requirements of the nuclear cladding tube port encapsulation are realized, making it suitable for use in harsh service environments. In this way, the leakage of the nuclear radiation of the cladding tube can be effectively prevented, and nuclear radiation leakage accidents can be prevented before they happen.

Description

technical field [0001] The invention belongs to nuclear energy nuclear fuel cladding tube packaging technology, and relates to a SiC f / SiC core cladding tube port CaO-Y 2 o 3 -Al 2 o 3 -SiO 2 Glass encapsulation methods, specifically SiC f / SiC core cladding tube ports CaO-Y 2 o 3 -Al 2 o 3 -SiO 2 The glass encapsulant and its encapsulation method are mainly used for port encapsulation and connection of nuclear cladding tubes. Background technique [0002] In 2011, a nuclear accident occurred at the Fukushima nuclear power plant in Japan. This was due to the zirconium alloy nuclear fuel cladding, which had a major safety hazard in the event of a dehydration accident in the reactor: the zirconium alloy cladding was rapidly oxidized in a high-temperature water vapor environment above 900°C, and gradually lost its mechanical properties. Performance and damage, resulting in core exposure and melting; at 1000 ℃, zirconium-water / steam react violently, producing a large...

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Problems solved by technology

[0002] In 2011, a nuclear accident occurred at the Fukushima nuclear power plant in Japan. This was due to the zirconium alloy nuclear fuel cladding, which had a major safety hazard in the event of a dehydration accident in the reactor: the zirconium alloy cladding was rapidly oxidized in a high-temperature water vapor environment above 900°C, and gradually lost its mechanical properties. performance and damage, resulting in core exposure and melting; at 1000 ° C, zirconium-water / steam react violently, producing a large amount of high-temperature combustible hydrogen and heat, resulting in severe hydrogen explosion and serious nuclear leakage accident

These service requirements greatly limit the packaging technologies that can be applied

So far, the commonly used packaging technology is difficult to meet the requirements of its mechanical properties and airtightness at the same time

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