Zr-Hf-Co合金储氢性能研究

谭功理; 刘晓鹏; 蒋利军; 王树茂; 李志念; 李华玲

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Zr-Hf-Co合金储氢性能研究

氢能研究 | 更新时间：2025-12-08

- Zr-Hf-Co合金储氢性能研究
- Dehydrogenation Characteristic of Zr-Hf-Co Alloy
- 西安交通大学学报 2007年41卷第11期页码：1380-1383
- 作者机构：
  
  北京有色金属研究总院能源材料与技术研究所,北京,100088
- 作者简介：
- 基金信息：
  
  : 2007-07-24. 作者简介: 谭功理(1982～),男,硕士生;刘晓鹏(联系人),男,高级工程师. 基金项目: 国家高技术研究发展计划资助项目(2006105Z1011)
- DOI：
  中图分类号： TK91
- 网络首发：2007-11-10，
  
  纸质出版：2007
- 稿件说明：
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谭功理, 刘晓鹏, 蒋利军, 等. Zr-Hf-Co合金储氢性能研究[J]. 西安交通大学学报, 2007,41(11):1380-1383.

谭功理, 刘晓鹏, 蒋利军, et al. Dehydrogenation Characteristic of Zr-Hf-Co Alloy[J]. 2007, 41(11): 1380-1383.
谭功理, 刘晓鹏, 蒋利军, 等. Zr-Hf-Co合金储氢性能研究[J]. 西安交通大学学报, 2007,41(11):1380-1383. DOI：

谭功理, 刘晓鹏, 蒋利军, et al. Dehydrogenation Characteristic of Zr-Hf-Co Alloy[J]. 2007, 41(11): 1380-1383. DOI：

摘要

研究了Hf部分替代Zr对Zr-Hf-Co合金储放氢性能的影响

结果表明:Zr-Hf-Co合金保持原始Zr-Co合金单一的立方相结构

且Hf含量变化对合金晶胞体积影响不大; 随Hf替代量增加

Zr-Hf-Co合金的放氢平台压升高

100 kPa平衡放氢压力对应的放氢温度显著降低

由Zr-Co合金的673 K降低到Zr

0.7

0.3

Co合金的618 K; 热力学计算结果得到Zr-Hf-Co合金的放氢反应焓变ΔH随Hf替代量增加而降低

表明Zr-Hf-Co合金氢化物的稳定性降低

有利于合金在较低温度下放氢; 合金的最大吸氢量随Hf替代量增加而略有降低

但吸氢动力学性能变化不明显.

Abstract

The intermetallic compound Zr

1-x

Co(x=0

0.1

0.2

0.3)was prepared and its suitability for hydrogen storage was investigated. The alloy remains with single cubic phase identical with Zr-Co by X-ray diffraction

and with increasing Hf content the lattice parameter of Zr-Hf-Co alloy varies slightly. Pressure-composition-temperature(PCT)measurement results show that the equilibrium dissociation pressure of Zr-Hf-Co alloy increases obviously with increasing Hf content. The dehydrogenation temperatures for supplying 100 kPa hydrogen are about 673

659

640

and 618 K for Zr-Co

0.9

0.1

0.8

0.2

and Zr

0.7

0.3

Co alloys

respectively. The thermodynamics calculation results indicate that in dehydrogenation ΔH for Zr-Hf

-Co alloy decreases with increasing Hf content

while ΔS is nearly constant

which are coincident with its dehydrogenation property. The maximal hydrogen storage capacity of Zr-Hf-Co alloy at room temperature decreases slightly with increasing Hf content

but the kinetic characters vary unremarkably.

关键词

Keywords

references

Shmayda W T, Heics A G, Kherani N P. Comparison of uranium and zirconium cobalt for tritium storage[J]. Journal of the Less-Common Metals, 1990, 162(1): 117-127.

Konishi S, Nagasaki T, Yokokawa N, et al. Development of zirconium-cobalt beds for recovery, storage and supply of tritium[J]. Fusion Engineering and Design, 1989, 10: 355-358.

Penzhorn R D, Devillers M, Sirch M. Evaluation of ZrCo and other getters for tritium handling and storage[J]. Journal of Nuclear Materials, 1990, 170(3): 217-231.

Naik Y, Rama Rao G A, Venugopal V. Zirconium-cobalt intermetallic compound for storage and recovery of hydrogen isotopes[J]. Intermetallics, 2001, 9(4): 309-312.

Hara M, Okabe T, Mori K, et al. Kinetics and mechanism of hydrogen-induced disproportionation of ZrCo[J]. Fusion Engineering and Design, 2000, 49/50: 831-838.

Konishi S, Nagasaki T, Okuno K. Reversible disproportionation of ZrCo under high temperature and hydrogen pressure[J]. Journal of Nuclear Materials, 1995, 223(3): 294-299.

Bekris N, Besserer U, Sirch M, et al. On the thermal stability of the zirconium/cobalt-hydrogen[J]. Fusion Engineering and Design, 2000, 49/50: 781-789.

Hara M, Hayakawa R, Kaneko Y, et al. Hydrogen-induced disproportionation of Zr2M(M=Fe, Co, Ni)and reproportionation[J]. Journal of Alloys and Compounds, 2003, 352(1/2): 218-225.

Konishi S, Nagasaki T, Hayashi T, et al. Equilibrium hydrogen pressure on the solid solutions of ZrCo-HfCo intermetallic compounds[J]. Journal of Nuclear Materials, 1995, 223(3): 300-304.

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