当前位置: X-MOL 学术J. Nucl. Mater. › 论文详情
Our official English website, www.x-mol.net, welcomes your feedback! (Note: you will need to create a separate account there.)
Temperature dependent electrochemical equilibrium diagram of zirconium-water system studied with density functional theory and experimental thermodynamic data
Journal of Nuclear Materials ( IF 2.8 ) Pub Date : 2020-02-04 , DOI: 10.1016/j.jnucmat.2020.152036
Guangxi Jin , Canhui Xu , Shuanglin Hu , Xiaosong Zhou

Zirconium (Zr) alloys are important cladding materials of nuclear fuel in nuclear power industry, which are commonly immersed in complicated aqueous environments. Their corrosion relates critically to the safe operation of nuclear reactors, and is affected by many factors. As a foundation to study such complicated corrosion behaviors, in this work, the electrochemical stabilities of various species in the Zr-water system are directly demonstrated with the electrochemical equilibrium (Pourbaix) diagrams. The diagrams are calculated by applying methods of combining first-principles calculations on solid state phases with experimental thermodynamic data of aqueous species. The calculated Pourbaix diagrams are generally consistent with the results of previous experiments, while the solid phases in the oxide form (passivation region) of the calculated ones are much richer than the experimental counterparts. The stabilities of the solid phases are significantly affected by temperature and acidity (pH value) of the environment, as well as slightly by ionic concentration. To construct the experimental consistent Pourbaix diagrams for the Zr-water system, it is found necessary to correct the relative chemical potentials between solids and aqueous ions. Such a scheme of correction is demonstrated to be robust for the Pourbaix diagrams obtained with different exchange-correlation functionals. This work may help us to understand the corrosion process more clearly and guide us to enhance the corrosion resistance of the cladding Zr in cooling water circuit environment.



中文翻译:

用密度泛函理论和实验热力学数据研究锆水体系随温度变化的电化学平衡图

锆(Zr)合金是核电工业中重要的核燃料包壳材料,通常浸入复杂的水环境中。它们的腐蚀与核反应堆的安全运行至关重要,并且受许多因素影响。作为研究此类复杂腐蚀行为的基础,在这项工作中,直接用电化学平衡图(Pourbaix)证明了Zr-水系统中各种物质的电化学稳定性。通过应用将固态相的第一性原理计算与水性物种的实验热力学数据相结合的方法来计算这些图。计算出的Pourbaix图通常与先前实验的结果一致,而所计算出的氧化物形式(钝化区)的固相比实验相的富集得多。固相的稳定性受环境温度和酸度(pH值)的影响很大,而离子浓度的影响也很小。为构建Zr-水系统的实验一致的Pourbaix图,发现有必要校正固体和水离子之间的相对化学势。对于使用不同交换相关函数获得的Pourbaix图,这种校正方案证明是可靠的。这项工作可以帮助我们更清楚地了解腐蚀过程,并指导我们增强包层Zr在冷却水回路环境中的耐腐蚀性。固相的稳定性受环境温度和酸度(pH值)的影响很大,而离子浓度的影响也很小。为构建Zr-水系统的实验一致的Pourbaix图,发现有必要校正固体和水离子之间的相对化学势。对于使用不同交换相关函数获得的Pourbaix图,这种校正方案证明是可靠的。这项工作可以帮助我们更清楚地了解腐蚀过程,并指导我们增强包层Zr在冷却水回路环境中的耐腐蚀性。固相的稳定性受环境温度和酸度(pH值)的影响很大,而离子浓度的影响也很小。为构建Zr-水系统的实验一致的Pourbaix图,发现有必要校正固体和水离子之间的相对化学势。对于使用不同交换相关函数获得的Pourbaix图,这种校正方案证明是可靠的。这项工作可以帮助我们更清楚地了解腐蚀过程,并指导我们增强包层Zr在冷却水回路环境中的耐腐蚀性。为构建Zr-水系统的实验一致的Pourbaix图,发现有必要校正固体和水离子之间的相对化学势。对于使用不同交换相关函数获得的Pourbaix图,这种校正方案被证明是健壮的。这项工作可以帮助我们更清楚地了解腐蚀过程,并指导我们增强在冷却水回路环境中覆层Zr的耐腐蚀性。为构建Zr-水系统的实验一致的Pourbaix图,发现有必要校正固体和水离子之间的相对化学势。对于使用不同交换相关函数获得的Pourbaix图,这种校正方案证明是可靠的。这项工作可以帮助我们更清楚地了解腐蚀过程,并指导我们增强包层Zr在冷却水回路环境中的耐腐蚀性。

更新日期:2020-02-04
down
wechat
bug