Zirconium alloy material for light water reactor under higher burnup

A zirconium alloy and weight technology, applied in the field of zirconium alloy materials, can solve the problems of decreased corrosion resistance, uneven growth, poor plastic processing ability of zirconium alloys, etc., to improve corrosion resistance, mechanical properties, and hydrogen absorption. performance effect
CN104745875AInactive Publication Date: 2015-07-01SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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Patent Information

Authority / Receiving Office
CN · China
Current Assignee / Owner
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
Publication Date
2015-07-01
Estimated Expiration
Not applicable · inactive patent

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Abstract

The invention discloses a zirconium alloy material for a light water reactor under higher burnup. The zirconium alloy material comprises 0.10-0.40 weight% of tin, 0.50-1.50 weight% of niobium, 0.01-0.20 weight% of iron and 0.06-0.20 weight% of oxygen, and further comprises 0.01-0.09 weight% of vanadium and / or 0.01-0.09 weight% of copper and the balance of zirconium. The zirconium alloy has excellent corrosion resistance; and compared with the zirconium alloy in the prior art, the zirconium alloy has more excellent corrosion resistance in high-temperature pure water, and is suitable for fuel rod cladding materials and corrosion resistant zirconium alloy materials of grillwork strips and structural parts under higher burnout of nuclear reactors.
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Description

technical field

[0001] The invention relates to an alloy material, in particular to a zirconium alloy material used in a light water reactor with relatively high burnup. Background technique

[0002] The earliest zirconium alloy used in pressurized water reactors is Zr-4 alloy. The average unloading fuel consumption of foreign pressurized water reactor fuel assemblies was 30-35GWd / tU in the late 1970s. The Sn content of the Zr-4 alloy is relatively high, ranging from 1.2 to 1.7%. Operation experience shows that high Sn content of the alloy is not good for corrosion resistance. Therefore, Westinghouse Corporation of the United States began to conduct research on ZIRLO alloys in the 1970s, and its Sn content was only 0.90-1.10%. As a Zr-Sn-Nb alloy, its Nb content is 0.80-1.20%, Fe content is 0.08-0.12%, and O content is 0.105-0.145%. When the internal combustion consumption of the PWR is 60GWd / tU, the corrosion resistance of the ZIRLO alloy is much better than that of the...

Claims

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