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Fecral-based alloy material for nuclear reactor cladding and preparation method thereof

A technology for nuclear reactors and base alloys, applied in the field of FeCrAl-based alloy materials for nuclear reactor cladding and its preparation, can solve the problems of difficult processing of alloy plates and thin-walled pipes, failure to meet the actual needs of industrialization, serious hardening and embrittlement, etc. Achieve excellent high-temperature oxidation resistance, high plasticity and toughness, and high tissue thermal stability

Active Publication Date: 2019-05-21
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] At present, most commercially available FeCrAl-based alloy materials have remarkable high-temperature oxidation resistance, but the degree of hardening and embrittlement is serious under thermal aging and irradiation conditions in reactor operating conditions, which brings major safety hazards to reactor operation.
Not only that, the commercial FeCrAl-based alloys have poor mechanical plasticity at room temperature, which makes it difficult to process alloy sheets and thin-walled pipes, and cannot meet the actual needs of industrialization.

Method used

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  • Fecral-based alloy material for nuclear reactor cladding and preparation method thereof
  • Fecral-based alloy material for nuclear reactor cladding and preparation method thereof
  • Fecral-based alloy material for nuclear reactor cladding and preparation method thereof

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Embodiment

[0030] Table 1 The composition ratio of the FeCrAl-based alloy embodiment of the present invention (the remainder is iron)

[0031]

[0032]

[0033] With the alloy material ratio of 1-7#, the preparation method is the same (that is, the parameters are exactly the same): the preparation method of the FeCrAl-based alloy material for the cladding of the advanced nuclear fuel element as described above specifically includes the following steps:

[0034] (1) prepare 20-30 kilograms of ingots with industrial pure iron and high-purity alloys with a purity greater than 99.9% according to the formula in Table 1;

[0035] (2) The above ingot is subjected to a high temperature homogenization annealing temperature. Annealing temperature: ≥1150°C, holding time ≥3h;

[0036] (3) Remove the oxide skin on the surface of the ingot after homogenization annealing, clean the surface and carry out high-temperature forging. The initial forging temperature is: ≥1050°C, the final forging temp...

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Abstract

The invention discloses a FeCrAl-based alloy material for nuclear reactor cladding, which comprises, by weight, Cr: 12.5-14.5%, Al: 3.5-5.5%, Mo: 2-3.5%, Nb: 1-2.5%, Si: 0.1 ~0.5%, Zr: 0~0.5%, Mn: 0~0.05%, La+Ce or La+Y: 0.01~0.1%, the balance is iron and impurities meeting industrial standards. The alloy material of the present invention has excellent high-temperature oxidation performance under the condition of 1000°C water vapor, the alloy has relatively high high-temperature strength and structural thermal stability at 800°C, and has very high mechanical strength and high thermal stability at room temperature Plastic toughness.

Description

technical field [0001] The invention belongs to the technical field of iron-based alloy structural materials and special alloy materials, and in particular relates to a FeCrAl-based alloy material for nuclear reactor cladding used in pressurized water reactors and a preparation method thereof. Background technique [0002] The fuel element is the core component of the nuclear power reactor core, and its performance is directly related to the safety and economy of the nuclear reactor operation. Zirconium alloy is currently the only cladding material used in commercial nuclear power light water reactor fuel elements. However, in emergencies (such as the Fukushima nuclear accident in Japan, the pressurized water reactor loss of water accident, etc.), the zirconium alloy cladding reacts violently with high-temperature coolant water, releasing a large amount of heat and explosive gas hydrogen, resulting in deterioration of the mechanical properties of the cladding material , res...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22C38/06C22C38/22C22C38/26C22C38/02C22C38/28C22C38/04C21D1/26C21D8/02C21D6/00
CPCC21D1/26C21D6/002C21D6/005C21D6/008C21D8/0226C21D8/0247C22C38/005C22C38/02C22C38/04C22C38/06C22C38/22C22C38/26C22C38/28
Inventor 张瑞谦王辉陈乐潘钱付陈勇刘超红王晓敏
Owner NUCLEAR POWER INSTITUTE OF CHINA