Radiation Induced Corrosion of Nuclear Fuel and Materials

Čuba, Václav; Múčka, V.; Pospı́šil, M.

doi:10.5772/32267

Cited by 4 publications

(4 citation statements)

References 59 publications

(71 reference statements)

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“…To date, the majority of studies of this complex system have focused on the chemical composition of the dissolution and the electrochemistry of the corrosion mechanism. 4,7,9,10,16 Since one of the most important factors driving oxidising conditions in the groundwater is the radiolysis of the water, 6,17 some studies have gone further and have attempted to replicate the radiolytic conditions electrochemically, 18,19 using external and dopant alpha sources 9,[20][21][22] and by the addition of H 2 O 2 to the groundwater solution. 6,10,23 This nal method is hotly debated amongst research groups, since it is not clear precisely what the H 2 O 2 concentration would be at the fuel surface.…”

Section: Introductionmentioning

confidence: 99%

Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO₂/water interface

et al. 2015

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X-ray diffraction has been used to probe the radiolytic corrosion of uranium dioxide. Single crystal thin films of UO(2) were exposed to an intense X-ray beam at a synchrotron source in the presence of water, in order to simultaneously provide radiation fields required to split the water into highly oxidising radiolytic products, and to probe the crystal structure and composition of the UO(2) layer, and the morphology of the UO(2)/water interface. By modeling the electron density, surface roughness and layer thickness, we have been able to reproduce the observed reflectivity and diffraction profiles and detect changes in oxide composition and rate of dissolution at the Ångström level, over a timescale of several minutes. A finite element calculation of the highly oxidising hydrogen peroxide product suggests that a more complex surface interaction than simple reaction with H(2)O(2) is responsible for an enhancement in the corrosion rate directly at the interface of water and UO(2), and this may impact on models of long-term storage of spent nuclear fuel.

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Section: Introductionmentioning

confidence: 99%

Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO₂/water interface

et al. 2015

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“…Once irradiation stops, the concentration of radiolytic species is dramatically decreased, although, the most stable among them, is hydrogen peroxide (H2O2), able to oxidize ferrous ions available in bulk solution via Fenton reaction (12):…”

Section: Commenté [Lg4]: Addition By Linas Version Comment 33mentioning

confidence: 99%

“…These chemical species, whose concentrations are dependent on LET (Linear Energy Transfer, defined as the amount of energy deposited by the charged particle along its path in solution) are prone to modify the physico-chemical conditions at the metal-water interface, and thus to impact the corrosion processes and the associated corrosion rate. Furthermore, these formed radiolytic species include H2 gas, meaning that porewater radiolysis will also lead to the additional production of this problematic gas [5,[12][13].…”

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confidence: 99%

“Impact of γ-radiation on carbon steel anaerobic corrosion and H2 production.”

Giannakandropoulou

Desjonquères

Wittebroodt

et al. 2023

Radiation Physics and Chemistry

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“…e occurrence of such a process leads to corrosion cracking and the ingress of fluid into parts. e process is complicated by the formation of ions and electrons (mainly OH − , H + , e − ) due to the radiolysis of water in storage of graphite RW [33][34][35]. It is worth noting that the formation of aluminum carbides does not occur at a regulated temperature of storage operating.…”

Section: Analysis Of Factors Initiating the Release Of Stored Energymentioning

confidence: 99%

Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite

Pavliuk

Bespala²,

Kotlyarevskiy

et al. 2022

Science and Technology of Nuclear Installations

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The article is dedicated to the safety assessment of mixed storage of irradiated graphite and other types of radioactive waste accumulated during the operation of uranium-graphite reactors. The analysis of heat release processes inside storages containing irradiated nuclear graphite, representing a potential hazard due to the possible heating and, accordingly, the release of long-lived radionuclides during oxidation was carried out. The following factors were considered as the main factors that can lead to an increase in the temperature inside the storage facility: corrosion of metallic radioactive waste, the presence of fuel fragments, and also the random exposure of irradiated graphite to local sources of thermal energy (spark, etc.). It was noted in the work that the combined or separate influence of some factors can lead to an increase in the temperature of the onset of the initiation of Wigner energy release in graphite radwaste (Tin ≈ 90–100°C for the “Worst-case” graphite). The model of heat generation in the storage was developed based on the analysis of the features of graphite radioactive waste storage and Wigner energy release. The layered location of different types of waste (graphite and aluminum) and the local character of the distribution of heat sources were adopted in this model. The greatest heating is achieved if graphite radioactive waste is located near the concrete walls of the storage facility, as well as in direct contact with irradiated aluminum radioactive waste, which was shown in this paper.

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Radiation Induced Corrosion of Nuclear Fuel and Materials

Cited by 4 publications

References 59 publications

Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO₂/water interface

Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO₂/water interface

“Impact of γ-radiation on carbon steel anaerobic corrosion and H2 production.”

Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite

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Radiation Induced Corrosion of Nuclear Fuel and Materials

Cited by 4 publications

References 59 publications

Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO2/water interface

Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO2/water interface

“Impact of γ-radiation on carbon steel anaerobic corrosion and H2 production.”

Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite

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Product

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Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO₂/water interface

Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO₂/water interface