1. Understanding the corrosion behaviour of metallic materials for the long-term containment of nuclear waste
- Author
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Smart, Nicholas R. and Scott, Tom
- Subjects
Corrosion ,Nuclear Waste ,Metallurgy & metallography ,Radiation ,Microbiology ,Bentonite ,Cement ,Copper ,Steel ,Anaerobic ,Hydrogen ,Disposal - Abstract
The unwanted corrosion of metal structures, objects and consumables has a significant global cost, which was estimated to be approximately $2.5T in 2017, which is equivalent to 3.4% of global GDP. Materials degradation by corrosion processes is an important issue in the nuclear industry. Since the advent of nuclear technology in the 1940s, radioactive waste has inevitably arisen, and this has resulted in strict controls being established to safely manage it over long periods. Extensive research into the storage and eventual disposal of such waste in deep, underground repositories has been undertaken around the world. This thesis describes the background to the generation of the various categories of radioactive waste and summarises the approaches that are taken globally to manage the waste. Metallic containers are a key component of the engineered barrier systems used to ensure that the human population is not exposed to harmful levels of radiation from radioactive waste. The materials of choice for waste packages range from so-called corrosion allowance metals, such as carbon steel and copper, to corrosion resistant alloys, such as stainless steel, nickel alloys and titanium. The corrosion behaviour of container materials, and the waste metals within the waste, has been an important area of study in the countries operating nuclear facilities. The environments to which the metal containers are exposed, range from atmospheric conditions during interim surface storage, and, after placement in an operating underground facility, to water-saturated anoxic conditions in contact with backfill materials, particularly cementitious materials or clay-type materials, such as bentonite, when the underground facility is finally sealed. It is necessary to obtain a thorough scientific understanding of the corrosion behaviour of container materials in these different environments, in addition to obtaining well-established values for corrosion rates in the expected conditions. This enables prediction of waste package durability over very long periods (>100 years). This D.Sc. thesis contains a summary of the author's previous work in this area and presents a set of over thirty published, peer-reviewed, corrosion science papers on the subject, which describe experimental studies undertaken by the author since the 1990s for a number of radioactive waste management organisations, both in the UK and overseas. The areas of study covered by the published papers presented here can be divided into two main categories, namely laboratory-based projects and in situ experiments. The main themes of the laboratory studies are: • Measurement of gas generation due to the anaerobic corrosion of ferrous materials, both in aqueous environments and when encapsulated in solid backfill materials such as cement and compacted bentonite, and characterisation of the arising corrosion products. • Investigation of the interactions between the corroding metal and the surrounding solid matrix, particularly bentonite. • The effect of -radiation on the corrosion of carbon steel in simulated waste storage and disposal environments. • Investigation of the possibility of expansive anoxic corrosion, caused by the formation of corrosion products on cast iron. • Electrochemical aspects of the anaerobic corrosion of steel • Galvanic corrosion of waste container metals and waste metals • Corrosion of steels in cement-based encapsulants. In situ studies have included the setting up, operation and analysis of several large-scale experiments in underground rock laboratories using a range of in-situ monitoring and analytical techniques. These have focused on: • Characterising the atmospheric corrosion of stainless steel radioactive waste containers, as a function of the prevailing environmental chemistry, using a full-scale prototype waste container. • The corrosion behaviour of copper, cast iron and carbon steel when exposed to real underground environments in Sweden and Switzerland and characterisation of the effect of corrosion on the surrounding bentonite. The overall aim of the laboratory and in situ the experiments was to determine corrosion rates, corrosion mechanisms and the characteristics of the corrosion products, so that the information derived could be used to support the preparation of operational guidance and safety cases for waste disposal facilities, for various national waste management organisations. The work presented in the papers within this thesis has led to the generation of new information and a deeper understanding relating to a number of different aspects of corrosion that are key to the safe storage and eventual disposal of radioactive waste, including: • The relationship between atmospheric environmental parameters during interim storage and the corrosion susceptibility of stainless steels. • The corrosion mechanism, corrosion rates and characteristics of the corrosion products formed during the long-term anaerobic corrosion of carbon steel in the most common backfill materials in a geological disposal facility, namely cementitious materials and compacted bentonite, and the effect of the corrosion products on the properties of the surrounding backfill materials. • The possible effects of -radiation on the corrosion behaviour of carbon steel under disposal conditions. • The mechanical properties of oxides formed during corrosion and the risk of expansive corrosion causing damage to waste containers under disposal conditions. • The characteristics of galvanic corrosion occurring between dissimilar metals in electrical contact in disposal environments. • The role of microbially influenced processes on the corrosion behaviour of container materials under realistic conditions during waste disposal. Finally, the thesis outlines possible future avenues of research to further develop the work presented in the published papers.
- Published
- 2023