Radiolytic corrosion of copper

铜的辐射腐蚀

• 批准号: 469090-2014
• 负责人: Shoesmith, David
• 金额: $ 8.45万
• 依托单位: University of Western Ontario
• 依托单位国家: 加拿大
• 项目类别: Collaborative Research and Development Grants
• 财政年份: 2016
• 资助国家: 加拿大
• 起止时间: 2016-01-01 至 2017-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=598398
• 关键词: Radiolytic; corrosion; copper

The present management scenario for the permanent disposal of high level nuclear waste is to bury it in sealed metallic containers buried in a deep stable geologic repository. The primary function of the waste container is to isolate the radioactive waste form from groundwater until radioactivity levels have decayed to innocuous levels. For the present thick-walled container design gamma radiation fields on the outside of the container would have a negligible influence on container corrosion. However, to overcome a number of fabrication and welding issues, thinner walled containers are being contemplated making a reassessment of the influence of gamma radiation on container corrosion a potential licensing requirement. This project addresses this issue by proposing a study of radiation effects on corrosion under simulated repository conditions, which will evolve from initially hot and dry to warm, aerated, and humid and eventually cool, aqueous and anoxic. A program of electrochemical, analytical and corrosion experiments will be employed to determine the mechanistic features of the corrosion process and to determine the evolution of corrosion damage as waste repository conditions evolve and radiation fields decay. A model will be developed to assess the extent to which the container wall can be thinned without compromising container corrosion performance.

目前高放核废料永久处置的管理方案是将其掩埋在密封的金属容器中，埋在深层稳定的地质处置库中。废物容器的主要功能是将放射性废物与地下水隔离，直到放射性水平衰减到无害水平。对于目前的厚壁容器设计，容器外部的伽马辐射场对容器腐蚀的影响可以忽略不计。然而，为了克服许多制造和焊接问题，正在考虑使用更薄壁的容器，从而重新评估伽马辐射对容器腐蚀的影响成为潜在的许可要求。该项目通过提出研究模拟储存库条件下的辐射对腐蚀的影响来解决这个问题，模拟储存库条件将从最初的炎热和干燥演变为温暖、通风和潮湿，最终发展为凉爽、含水和缺氧。将采用电化学、分析和腐蚀实验程序来确定腐蚀过程的机械特征，并确定随着废物储存库条件的变化和辐射场衰减而腐蚀损坏的演变。将开发一个模型来评估在不影响容器腐蚀性能的情况下容器壁可以减薄的程度。