Corrosion Issues Related to Disposal of High-Level Nuclear Waste in the Yucca Mountain Repository—Peer Reviewers' Perspective

Duquette, D. J.; Latanision, R. M.; Bella, C. A. W. Di; Kirstein, B.E.

doi:10.5006/1.3319133

Cited by 15 publications

(12 citation statements)

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“…These canisters will be enclosed within waste packages and then emplaced in a mined underground geologic repository, which is the approach planned by most countries with such waste 2 . In the U.S. program, the current waste package design includes glass being cast into SS 304 canisters then encased in a SS 316 inner shell and an Alloy 22 outer shell 3,4 . The repository system is designed to isolate the highly radioactive waste from humans for hundreds of thousands of years 4 .…”

Section: Introductionmentioning

confidence: 99%

Near-field corrosion interactions between glass and corrosion resistant alloys

et al. 2020

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This study explores the corrosion interactions between model nuclear waste glass materials and corrosion resistant alloys, under accelerated conditions that simulate the near field of a nuclear waste repository. The interactions between the corrosion of stainless steel (SS) 316, alloy G30, or alloy 625, and international simple glass or soda-lime silica glass are systematically studied. The dissimilar materials were exposed in close proximity to each other in different electrolytes at 90°C. After exposure, the glass surface exposed near metals showed different regimes of corrosion, with distinct surface morphologies and chemistries that were likely affected by the local environment created by the localized corrosion of metals. Surface and solution analyses showed that the corrosion rate of glass was enhanced by the presence of metals. Infrared spectroscopy data suggested the local build-up of stresses in the contact area of glass, which may lead to the mechanical instability of the glass alteration layer. On the other hand, the effect of glass on metal corrosion is strongly dependent on the leaching solution. In electrolytes containing abundant aggressive anions such as Cl − , glass seems to suppress the localized corrosion of SS by the precipitation of a Si-rich surface film that protects the SS substrate from solutions. However, in less aggressive electrolytes, the corrosion rate of SS was increased by the presence of glass corrosion products. Overall, our study showed that the hidden and localized damage on glass in contact with metals may enhance the release rate of glass components compared to typical uniform glass corrosion.

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Section: Introductionmentioning

confidence: 99%

Near-field corrosion interactions between glass and corrosion resistant alloys

et al. 2020

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“…The International Atomic Energy Agency (IAEA) has proposed nine fundamental principles in radioactive waste disposal management which aims to isolate high-level radioactive waste from biosphere safely and permanently or at least maintain stability during the disposal period up to hundreds of thousands of years or even millions of years [2][3]. Deep geological disposal with a 'multi-barrier system' that consists of wastes which are vitrified, packing materials, backfill materials and surrounding rocks is currently generally accepted by many countries [4][5][6].…”

Section: Introductionmentioning

confidence: 99%

Corrosion behaviour of carbon steel, titanium and titanium alloy in simulated underground water in Beishan area preselected for nuclear waste repository in China

Zhang

Huang

Nishikata

et al. 2017

Corrosion Engineering, Science and Technology

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The groundwater will completely infiltrate to the surface of nuclear waste container after the closure of its deep geological disposal. Therefore, the corrosion behaviour of Q235 carbon steel, titanium and titanium alloy, which were the candidates as the container materials for high-level nuclear waste disposal in simulated groundwater solution of Beishan to be served as the preselected high-level nuclear waste disposal area in China at different temperatures, was studied through electrochemical methods including open circuit potential, electrochemical impedance spectroscopy and potentiodynamic polarisation curve measurements. The results show that the corrosion rate of titanium and titanium alloy is lower than that of carbon steel at all temperatures, and they are more promising as container materials. Another phenomenon is that higher temperatures facilitate the protection performance of corrosion products compared with lower temperatures.

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“…C-22 showed excellent corrosion resistance when used in a DGR. Duquette et al [49] discussed the corrosion related to HLW decommissioning in the Yucca Mountain repository. Another study focused on metal containers intended for the decommissioning of solid RW [50].…”

Section: Deep Geologic Repositorymentioning

confidence: 99%

Investigation into the Current State of Nuclear Energy and Nuclear Waste Management—A State-of-the-Art Review

Alwaeli

Mannheim

2022

Energies

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Nuclear power can replace fossil fuels and will have a decisive impact on the change in the approach to conventional energy. However, nuclear (or radioactive) wastes are produced by the operation of the nuclear reactors should be safely and properly disposed of. This paper assesses the uranium resources and the global state of nuclear power plants and determines the energy mixes in different countries using the most nuclear energy. Furthermore, this paper analysed the nuclear waste management and disposal and the depletion of abiotic resources, and the primary energy sources of a basic production process using electricity mix and nuclear electricity for a basic production (PET bottle manufacturing) process. The life cycle assessment was completed by applying the GaBi 8.0 (version 10.6) software and the CML method. In this study, we limit our discussion to high-level nuclear waste (HLW) and spent nuclear fuel (SNF) waste. We do not consider waste generated from uranium mining and milling, which is usually disposed of in near-surface impoundments close to the mine or the mill. The investigation of waste management methods is limited to European countries. This research work is relevant because determining abiotic resources is important in a life cycle assessment and current literature available on LCA analysis for nuclear powers remains under-developed. These results can guide and compare manufacturing processes involving a nuclear electricity and electricity grid mix input. The results of this research can be used to develop production processes using nuclear energy with lower abiotic depletion impacts. This research work facilitates the industry in making predictions for a production-scale plant using an LCA of production processes with nuclear energy consumption.

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Corrosion Issues Related to Disposal of High-Level Nuclear Waste in the Yucca Mountain Repository—Peer Reviewers' Perspective

Cited by 15 publications

References 0 publications

Near-field corrosion interactions between glass and corrosion resistant alloys

Near-field corrosion interactions between glass and corrosion resistant alloys

Corrosion behaviour of carbon steel, titanium and titanium alloy in simulated underground water in Beishan area preselected for nuclear waste repository in China

Investigation into the Current State of Nuclear Energy and Nuclear Waste Management—A State-of-the-Art Review

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