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Zirconium Niobium Alloys for Reactor Nuclear Fuel Assemblies

A technology for nuclear fuel assemblies and zirconium-niobium alloys, which is applied in the field of zirconium-niobium alloys, can solve the problems of high corrosion resistance, high fuel consumption, failure of fuel rod cladding structure, deviation from nucleate boiling, etc., and achieves low cost and high yield. , reduce the effect of corrosion and weight gain

Active Publication Date: 2015-09-23
CHINA NUCLEAR POWER TECH RES INST CO LTD +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0008] Although the third-generation zirconium alloy has better corrosion resistance than the second-generation low-tin Zr-4 alloy, its composition is not optimal, and its corrosion resistance cannot meet the high fuel consumption and long-term use conditions (such as 18 Monthly refueling) anti-oxidation requirements; excessive thickening of the oxide film and boil-like corrosion will lead to the failure of the fuel rod cladding structure, the occurrence of departure from nucleate boiling (DNB) and the risks of cladding burnout, etc.

Method used

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  • Zirconium Niobium Alloys for Reactor Nuclear Fuel Assemblies

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Embodiment Construction

[0022] Several different preferred embodiments of the present invention will be described below.

[0023] The essence of the present invention is to provide a zirconium-niobium alloy for reactor nuclear fuel assembly, which includes the following components based on the weight percentage of the zirconium-niobium alloy: 0.9% to 1.1% of Nb, 0.15% to 0.35% of Fe, and 0.1% ~0.16% O, and 0.004%~0.01% Cu, except for unavoidable impurities, the balance being Zr. Among them, Nb, Fe, O, and Cu are strengthening elements. In the present invention, the strengthening effect brought by these strengthening elements is sufficient, otherwise the zirconium-niobium alloy will be significantly strengthened and its toughness will be reduced, and it will be easy to crack during the extrusion process of the tube blank This leads to a decrease in the yield of good products, or even damage to equipment, so the content of each strengthening element in the zirconium-niobium alloy of the present inventi...

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Abstract

The invention provides a zirconium-niobium alloy for a nuclear fuel component of a reactor. The zirconium-niobium alloy comprises the following components by weight: 0.9-1.1% of Nb, 0.15-0.35% of Fe, 0.1-0.16% of O, 0.004-0.01% of Cu, inevitable impurities and the balance of Zr. The zirconium-niobium alloy is high in mechanical strength, and good in corrosion resistance.

Description

technical field [0001] The invention relates to the field of zirconium alloy materials, in particular to zirconium-niobium alloys used for reactor nuclear fuel assemblies. Background technique [0002] The reactor nuclear fuel assembly is a key component of the reactor core, including guide tubes, cladding of fuel rods, upper end plugs, lower end plugs, inner and outer strips of the assembly grid, etc. The main function is to protect the fuel pellets from coolant erosion , release energy, and shield strong radioactive substances from leaking. During operation, nuclear fuel assemblies need to withstand threats such as high internal and external pressure, high temperature, fuel swelling, and embrittlement caused by hydrogen absorption. According to. Therefore, nuclear fuel assemblies need to meet the performance requirements of metallurgy, heat transfer, machinery, etc., such as: (1) small neutron absorption cross section, good radiation stability; (2) sufficient room temper...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22C16/00G21C3/07
CPCY02E30/40Y02E30/30
Inventor 谭军邹红李锐陈建新温敦古陈刘涛杨建伟张波生
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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