Fe-cr-al alloy for nuclear reactor fuel element cladding material and preparation method thereof
A technology for nuclear reactor fuel and cladding material, which is applied to reactor fuel elements, reactors, nuclear engineering, etc., can solve problems such as swelling, reactor accident, rupture, etc., achieve simple operation, withstand swelling force, achieve safety and impact resistance performance effect
Active Publication Date: 2021-05-07
SHANGHAI UNIV +1
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Problems solved by technology
However, in 2011, a dehydration accident occurred in Fukushima, Japan. The Zr alloy cladding swelled and ruptured in a high-temperature environment, and Zr reacted violently with high-temperature water vapor, releasing a large amount of heat and explosive gas H. 2 , leading to a reactor accident
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Embodiment 1
[0026] In the present embodiment, a kind of Fe-Cr-Al alloy for nuclear reactor fuel element cladding material, the chemical composition of this alloy is calculated as following table 1 by weight percentage, represents the present embodiment Fe-Cr-Al alloy and Zr-1Nb alloy Composition:
[0027] Table 1. Example 1 Fe-Cr-Al alloy and comparative example Zr-1Nb alloy composition comparison table
[0028]
[0029] Alloy No. 1-4 alloys with the composition of the above table 1 are prepared according to the following steps:
[0030] (1) according to the chemical composition of No. 1-4 alloy in above-mentioned table 1, weigh raw material with percentage by weight, raw material selects high-purity metal material, with vacuum non-consumable electric arc furnace, mixed raw material is smelted into 60g ingot;
[0031] (2) heating the ingot prepared in the step (1) to 1000-1050° C., keeping it warm for 20 minutes, and hot-pressing it 5 times to obtain a pre-heat-treated alloy material;...
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Abstract
The invention discloses a Fe-Cr-Al alloy for nuclear reactor fuel element cladding material and a preparation method thereof. The chemical composition of the Fe-Cr-Al alloy is calculated by weight percentage: Cr: 10-26%; Al: 3-10%; Mo: 1-5.5%; Nb: 0.01-5.5%; the balance is Fe and impurities . Nb element is added to the Fe-Cr-Al alloy of the present invention, and the Fe-Cr-Al alloy shows excellent corrosion resistance in the simulated nuclear reactor conventional corrosion environment, and also shows excellent corrosion resistance in the simulated LOCA working condition high-temperature steam oxidation environment. Oxidation resistance, its corrosion resistance / oxidation resistance is significantly better than that of Zr‑1Nb alloys, and it has better accident tolerance than zirconium alloys. It is used as nuclear fuel element cladding materials and nuclear fuel element composite cladding materials in nuclear power plant pressurized water reactors And core structural materials such as spacer grid strips.
Description
technical field [0001] The invention relates to an Fe-Cr-Al alloy and a preparation method thereof, in particular to a high-temperature-resistant steam oxidation Fe-Cr-Al alloy and a preparation method thereof, which are applied in the technical field of nuclear fuel element materials. Background technique [0002] Zirconium alloys, as cladding materials for traditional nuclear fuel elements, exhibit a series of excellent properties. However, in 2011, a dehydration accident occurred in Fukushima, Japan. The Zr alloy cladding swelled and ruptured in a high-temperature environment, and Zr reacted violently with high-temperature water vapor, releasing a large amount of heat and explosive gas H. 2 , resulting in a reactor accident. Zr alloy cladding materials are exposed to insufficient oxidation resistance and mechanical properties in high temperature environments greater than 800 ° C. Therefore, a solution is proposed to develop accident tolerant fuel (Accident Tolerant Fuel,...
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IPC IPC(8): C22C38/26C22C38/22C22C38/06C22C33/04C21D8/02C21D1/26G21C3/07
CPCC21D1/26C21D8/0205C21D8/0226C21D8/0231C22C33/04C22C38/06C22C38/22C22C38/26G21C3/07Y02E30/30
Inventor 姚美意钱月孙蓉蓉张文怀瞿忱张金龙杨健仇云龙
Owner SHANGHAI UNIV