Interaction of hydrogen with radiolysis products in NaCl solution — comparing pulse radiolysis experiments with simulations

Kelm, M.; Metz, Volker; Bohnert, E.; Janata, E.; Bube, C.

doi:10.1016/j.radphyschem.2010.10.011

Cited by 11 publications

(9 citation statements)

References 58 publications

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“…The coefficient for seawater was calculated based on the reported composition [17]. The coefficient for the mordenite was calculated from the chemical formula of the type material, Na 8 (H 2 O) 24 Al 8 Si 40 O 96 .…”

Section: Dosimetrymentioning

confidence: 99%

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Hydrogen production in gamma radiolysis of the mixture of mordenite and seawater

Kumagai

Kimura

Taguchi

et al. 2013

Journal of Nuclear Science and Technology

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Hydrogen production by g-radiolysis of the mixture of mordenite, a zeolite mineral, and seawater was studied in order to provide basic points of view for the influences of zeolite minerals, of the salts in seawater, and of rise in temperature on the hydrogen production by the radiolysis of water. These influences are required to be considered in the evaluation of the hydrogen production from residual water in the waste zeolite adsorbents generated in Fukushima Dai-ichi Nuclear Power Station. As the influence of the mordenite, an additional production of hydrogen besides the hydrogen production by the radiolysis of water was observed. The additional hydrogen can be interpreted as the hydrogen production induced by the absorbed energy of the mordenite at the yield of 2.3610 78 mol/J. The influence of the salts was observed as increase of the hydrogen production. The influence of the salts can be attributed to the reactions of bromide and chloride ions inhibiting the reaction of hydrogen with hydroxyl radical. The influence of the rise in temperature was not significantly observed up to 608C in the mixture with seawater. The results show that the additional production of hydrogen due to the mordenite had little temperature dependence.

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Section: Dosimetrymentioning

confidence: 99%

“…The radicals involved in the reaction processes subsequent to reactions (R2) [24] and (R3) [25] are reported to be scarcely reactive with H 2 . In addition, the H 2 production through reactions of hydrated electron (e 7 aq ) and hydrogen atom (H . )…”

Section: H 2 Production From Seawatermentioning

confidence: 99%

Hydrogen production in gamma radiolysis of the mixture of mordenite and seawater

Kumagai

Kimura

Taguchi

et al. 2013

Journal of Nuclear Science and Technology

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“…In a recent pulse radiolysis study, Kelm et al [80] confirmed that H 2 interacts radiation chemically solely with the OH radical to produce oxidizing longlived radiolysis products. Though Br − is a minor constituent in groundwater of deep geological formations, it is present in a concentration range relevant for radiolytic processes, i.e.…”

Section: Radiolysis Of Aqueous Solutionmentioning

confidence: 99%

“…Leaching experiments with SNF samples and non irradiated UO 2 (s) as well as radiolysis studies indicate that molecular hydrogen both impedes radiolytic decomposition of the diluted and saline solutions and considerably inhibits corrosion of the UO 2 (s) matrix [71,73,80,85,90,[124][125][126][127][128][129][130][131][132]. Fig.…”

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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“…These conditions are also relevant under certain reactor accident scenarios where large amounts of Sea water are pumped into reactors and storage pools to maintain cooling [4] . A number of experimental studies on the radiation chemistry of water containing high concentrations of Cl − have been reported in the literature [14–31] and there are also several examples of studies of radiation induced dissolution of UO 2 or used nuclear fuel under similar conditions [32,33] . At high halide concentrations, the dominating oxidant in the system may not be H 2 O 2 [22,30,32,33] .…”

Section: Introductionmentioning

confidence: 99%

H₂O₂‐Induced Oxidative Dissolution of UO₂ in Saline Solutions

Jamal

Jönsson

2021

Eur J Inorg Chem

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H2O2 is one of the oxidants responsible for driving the process of radiation‐induced dissolution of spent nuclear fuel in geological repositories for spent nuclear fuel. As the groundwater composition will vary depending on geographical location as well as on the age of the repository (in relation to glacial cycles, etc.), it is important to elucidate the impact of different groundwater constituents. While several studies have addressed the impact of HCO3− and halide ions on the radiation chemistry of water in general and radiation‐induced oxidative dissolution of spent nuclear fuel in particular, very few studies have addressed the impact of halide ions on the mechanism of the reaction between H2O2 and UO2. In this work, the impact of Cl−, Br− and ClO4− on the mechanism and kinetics of H2O2‐induced oxidative dissolution of UO2‐powder in aqueous suspensions with and without added HCO3− has been studied experimentally. The experiments reveal both ionic strength effects and specific ion effects on the kinetics of the reactions involved. These are discussed in connection to the results.

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Interaction of hydrogen with radiolysis products in NaCl solution — comparing pulse radiolysis experiments with simulations

Cited by 11 publications

References 58 publications

Hydrogen production in gamma radiolysis of the mixture of mordenite and seawater

Hydrogen production in gamma radiolysis of the mixture of mordenite and seawater

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

H₂O₂‐Induced Oxidative Dissolution of UO₂ in Saline Solutions

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Interaction of hydrogen with radiolysis products in NaCl solution — comparing pulse radiolysis experiments with simulations

Cited by 11 publications

References 58 publications

Hydrogen production in gamma radiolysis of the mixture of mordenite and seawater

Hydrogen production in gamma radiolysis of the mixture of mordenite and seawater

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

H2O2‐Induced Oxidative Dissolution of UO2 in Saline Solutions

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Product

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H₂O₂‐Induced Oxidative Dissolution of UO₂ in Saline Solutions