Corrosion of irradiated MOX fuel in presence of dissolved H2

Carbol, Paul; Fors, Patrik; Winckel, Stefaan Van; Spahiu, Kastriot

doi:10.1016/j.jnucmat.2009.03.044

Cited by 37 publications

(27 citation statements)

References 37 publications

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“…An H 2 pressure of 50 bar (725 psi) has been predicted to be generated from the anoxic corrosion of the iron canisters by groundwater (Cui et al 2012). Dissolved hydrogen at low temperature is chemically inert and can significantly contribute to establishing reducing conditions in the near field (Carbol et al 2009, Ekeroth et al 2006, Jégou et al 2005) and effectively shutting down the UO 2 oxidation process.…”

Section: Model Descriptionmentioning

confidence: 99%

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Radiolysis Process Model

Buck¹,

Wittman²,

Skomurski³

et al. 2012

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SUMMARYThis report satisfies the Used Fuel Disposition M3 Milestone, Radiolysis Products Modeling Results for Scenarios, (M3FT-12PN080651).Assessing the performance of Spent (or Used) Nuclear Fuel (UNF) in geological repository requires quantification of time-dependent phenomena that may influence its behavior on a time-scale up to millions of years. A high-level waste repository environment will be a dynamic redox system because of the time-dependent generation of radiolytic oxidants and reductants and the corrosion of Fe-bearing canister materials. One major difference between used fuel and natural analogues, including unirradiated

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Section: Model Descriptionmentioning

confidence: 99%

“…Consideration of H 2 formation in the water just from radiolysis may not to be sufficient to describe the experimentally observed H 2 effect (Carbol et al 2009). Experiments by Pastina and LaVerne (2001) differences are expected when comparing long-term solubility or rate control.…”

Section: Hydrogenmentioning

confidence: 99%

Radiolysis Process Model

Buck¹,

Wittman²,

Skomurski³

et al. 2012

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“…A significant H 2 pressure has been predicted to be generated due to the anoxic corrosion of the iron canisters. Dissolved hydrogen can significantly contribute to establishing reducing conditions in the near field [21][22][23] and effectively suppressing the UO 2 oxidation process even in the presence of a high alpha field. …”

Section: Discussionmentioning

confidence: 99%

Simulation of alpha dose for predicting radiolytic species at the surface of spent nuclear fuel pellets

Becker

Kienzler

2014

Open Chemistry

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In many countries, spent nuclear fuel is considered as a waste form to be disposed of in underground disposal. Under deep host rock conditions, a reducing environment prevails. In the case of water contact, long-term radionuclide release from the fuel depends on dissolution processes of the UO 2 matrix. The dissolution rate of irradiated UO 2 is controlled by oxidizing processes facilitated by dissolved species formed by alpharadiolysis of water in contact with spent nuclear fuel. To understand the effect of the radiation, the information of the dose rate at the surface of the fuel and its proximity is needed. α particles contribute strongly due to their high linear energy transfer. However, their dose rate and the energy deposition at the fuel surface are difficult to measure. Cylindrical fuel pellets as used in fuel rods show specific features, such as the rim zone, where a higher Pu concentration and a different porosity of the fuel matrix is present. The a particle dose rate was determined by simulations with the code MCNPX with focus on the rim zone of a pellet. As a result a 40% increased dose level in the rim zone exists in comparison to the center of a pellet. The potential dominant and inhomogeneous α-dose distribution is supposed to have a strong impact on radiolysis phenomena and in turn on an inhomogeneous dissolution of elements over the surface.

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“…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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Corrosion of irradiated MOX fuel in presence of dissolved H2

Cited by 37 publications

References 37 publications

Radiolysis Process Model

Radiolysis Process Model

Simulation of alpha dose for predicting radiolytic species at the surface of spent nuclear fuel pellets

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

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