Hydrogen storage isotopic sc-cr-mn alloys with high activity and high resistance to hydrogen-induced disproportionation

Abstract

The invention relates to a high activity and high hydrogen-induced disproportionation resisting hydrogen storage isotope Sc-Cr-Mn alloy, which is characterized in that: it has a general formula: Scx(CryMn1-y)2, wherein x is greater than or equal to 0.85 and is smaller than or equal to 1.15, and y is greater than or equal to 0.35 and is smaller than or equal to 0.65. The alloy can absorb hydrogen directly under room temperature and 0.5KPa without high temperature or high pressure pretreatment activation. Under a room temperature and an intense pressure of 0.1MPa, the hydrogen storage capacity can be 2.5wt%. The room temperature hydrogen absorption equilibrium pressure is lower than 0.01Pa, and the complete desorption temperature of hydrogen is lower than 400DEG C. When the temperature is raised to over 200DEG C, the hydrogen absorption and hydrogen desorption kinetic curves of the alloy are consistent, the phenomena of lagging hydrogen absorption and desorption and hydrogen-induced disproportionation do not exist. The formed hydride has high crystallinity, good chalking resistance as well as strong anti-poisoning ability, and does not ignite spontaneously. Thus, the alloy provided in the invention is suitable for storage and transportation of isotope hydrogen, deuterium and tritium.

Description

technical field [0001] The invention relates to a hydrogen storage isotope alloy material, in particular to a hydrogen storage isotope Sc-Cr-Mn alloy with high activity and high resistance to hydrogen-induced disproportionation. Background technique [0002] There are two ways for humans to use nuclear energy: heavy nuclear fission and light nuclear fusion. Tritium is both a by-product of heavy nuclear fission reactors and a necessary reactant for light nuclear fusion. It is of great significance to solve the needs of tritium recovery, storage and transportation, and supply for light nuclear fusion in nuclear fission reactors. [0003] In the 1950s and 1960s, metal U became a tritium storage material commonly used in nuclear reactors. With the emergence of U safety issues and the high tritium storage performance of ZrCo alloys, since the 1990s, international thermonuclear fusion experiments ITER uses ZrCo alloy as a substitute material for U in the storage, separation and ...

AI Technical Summary

Problems solved by technology

The maximum hydrogen storage capacity of the ZrCo alloy is 1.9wt%. In order to completely release the hydrogen atoms in the alloy, the temperature must be raised. Obvious hysteresis, and when the temperature continues to rise, the amount of hydrogen released by the alloy hydride generated by the hydrogen absorption decreases sharply with time, and the hydrogen of the alloy cannot be completely released, which is the so-called high-temperature hydrogen-induced disproportionation phenomenon. This phenomenon limits The large-scale application of the alloy in the separation and purification of tritium

The previously announced Zr-Co-M (M=Ti or Hf) alloy (patent application number: 200810239961.2) has a maximum hydrogen storage capacity of not less than 1.7wt%, and the hydrogen release must increase the temperature to above 400°C. Although the alloy is at 0.10 The resistance to hydrogen-induced disproportionation under MPa initial pressure and 673K ​​service conditions is more than 4 times higher than that of ZrCo alloys, but hydrogen-induced disproportionation behavior still occurs at high temperatures in the end

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