The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions

Broczkowski, Michael E.; Noël, James J.; Shoesmith, David W.

doi:10.1016/j.jnucmat.2005.04.070

Cited by 89 publications

(55 citation statements)

References 16 publications

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“…Electrochemical experiments have shown that the corrosion potential of SIMFUEL containing noble metal inclusions drops drastically in the presence of H 2 [71]. On the basis of this observation a reaction where the noble metal inclusions catalyze the reduction of U(VI) to U(IV) by H 2 on the surface of the pellet was postulated [71]. This reaction was later verified using Pd particle-doped UO 2 pellets exposed to H 2 O 2 and H 2 [59].…”

Section: Influence Of Groundwater Componentsmentioning

confidence: 93%

“…The process becomes much faster in the presence of a catalyst, such as Pd particles [70]. Electrochemical experiments have shown that the corrosion potential of SIMFUEL containing noble metal inclusions drops drastically in the presence of H 2 [71]. On the basis of this observation a reaction where the noble metal inclusions catalyze the reduction of U(VI) to U(IV) by H 2 on the surface of the pellet was postulated [71].…”

Section: Influence Of Groundwater Componentsmentioning

confidence: 99%

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Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Jönsson

2012

ISRN Materials Science

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Safe long-term storage of radioactive waste from nuclear power plants is one of the main concerns for the nuclear industry as well as for governments in countries relying on electricity produced by nuclear power. A repository for spent nuclear fuel must be safe for extremely long time periods (at least 100 000 years). In order to ascertain the long-term safety of a repository, extensive safety analysis must be performed. One of the critical issues in a safety analysis is the long-term integrity of the barrier materials used in the repository. Ionizing radiation from the spent nuclear constitutes one of the many parameters that need to be accounted for. In this paper, the effects of ionizing radiation on the integrity of different materials used in a granitic deep geological repository for spent nuclear fuel designed according to the Swedish KBS-3 model are discussed. The discussion is primarily focused on radiationinduced processes at the interface between groundwater and solid materials. The materials that are discussed are the spent nuclear fuel (based on UO 2 ), the copper-covered iron canister, and bentonite clay. The latter two constitute the engineered barriers of the repository.

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Section: Influence Of Groundwater Componentsmentioning

confidence: 93%

Section: Influence Of Groundwater Componentsmentioning

confidence: 99%

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Jönsson

2012

ISRN Materials Science

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“…Depending on these SNF properties, the IRF comprises few percent of the inventories of fission gases (Kr and Xe), other volatiles fission products ( 129 I, 137 Cs, 135 Cs, 79 Se) and segregated metals ( 99 Tc, 107 Pd, 126 Sn) [102]. Additionally, some of the activation products from the cladding and fuel assembly structural materials notably 14 C and 36 Cl, are considered to be subject to a fast release upon contact with aqueous solution.…”

Section: Fast/instant Release Of Radionuclides From Spent Nuclear Fuelmentioning

confidence: 99%

“…Leaching experiments with SNF and UO 2 (s) samples as well as electrochemical studies in diluted Na + -Cl − -HCO 3 − / CO 3 2− solutions demonstrate clearly a hydrogen inhibition effect mediated by Ru-Pd-Rh-doping and ε-particles [133][134][135][136][137][138][139]]. An ε-particle surface mediated hydrogen effect depends on the availability of these particles and might be affected by "poisoning" of these noble metal alloys with dissolved sulfides present in the near-field, whereas a radiolytic driven hydrogen effect will be weakened by counteracting groundwater constituents, such as bromide.…”

Section: Radionuclide Release Due To Corrosion Of the Uo 2 Matrixmentioning

confidence: 99%

Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel

et al. 2012

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UO 2 fuel corrosion / Radionuclide release / Instant release fraction / Hydrogen effect / Coprecipitation / SorptionSummary. Even though chemical processes related to the corrosion of spent nuclear fuel in a deep geological repository are of complex nature, knowledge on underlying mechanisms has very much improved over the last years. As a major result of numerous studies it turns out that alteration of irradiated fuel is significantly inhibited under the strongly reducing conditions induced by container corrosion and consecutive H 2 production. In contrast to earlier results, radiolysis driven fuel corrosion and oxidative dissolution appears to be less relevant for most repository concepts. The protective hydrogen effect on corrosion of irradiated fuel has been evidenced in many experiments. Still, open questions remain related to the exact mechanism and the impact of potentially interfering naturally occurring groundwater trace components. Container corrosion products are known to offer considerable reactive surface area in addition to engineered buffer and backfill material. In combination, waste form, container corrosion products and backfill material represent strong barriers for radionuclide retention and retardation and thus attenuate radionuclide release from the repository near-field.

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“…Noble metal fission products present in the spent nuclear fuel are known to congregate to nanometersized particles (e-particles) [27]. These particles can act as catalysts for oxidation of U(IV) and reduction of U(VI) by H 2 on the surface/in the solid phase [28][29][30]. The effect of Pd-inclusions (as a substitute for e-particles) and irradiation on the rate constants for oxidation of UO 2 by O 2 and H 2 O 2 and reduction of UO 2 2?…”

Section: Factors Influencing the Solid Phase Reactivitymentioning

confidence: 99%

Factors influencing the rate of radiation-induced dissolution of spent nuclear fuel

2009

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Several countries plan to store spent nuclear fuel in deep geological repositories. Accurate prediction of the spent fuel dissolution rate is a key issue in the safety assessment of a future deep repository. A reliable quantitative model for radiation-induced spent fuel dissolution must be based on an accurate description of the dose distribution around the spent fuel and fundamental knowledge about the elementary processes involved. In this paper, we discuss factors influencing the rate of radiation-induced dissolution of spent nuclear fuel, focusing on solutes (H 2 , HCO 3 -, Fe(II) and organic substances affecting the H 2 O 2 concentration and factors influencing the reactivity of the fuel surface towards H 2 O 2 . Taking these factors into account, we have also simulated dissolution of spent nuclear fuel under realistic deep repository conditions.

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The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions

Cited by 89 publications

References 16 publications

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel

Factors influencing the rate of radiation-induced dissolution of spent nuclear fuel

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