The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2

Stroes-Gascoyne, S.; Garisto, Frank; Betteridge, J.S.

doi:10.1016/j.jnucmat.2005.04.069

Cited by 21 publications

(10 citation statements)

References 10 publications

(19 reference statements)

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“…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 (Stroes-Gascoyne et al 2005, Shoesmith et al 2003. One major difference between used fuel and natural analogues, including unirradiated UO 2 , is the intense radiolytic field.…”

Section: Model Descriptionmentioning

confidence: 99%

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%

Radiolysis Process Model

Buck¹,

Wittman²,

Skomurski³

et al. 2012

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“…Several different types of materials have been manufactured and tested in dissolution experiments. UO 2 doped with α-emitting nuclides [51][52][53][54][55][56][57][58] has been used to mimic the radiation field from spent nuclear fuel older than 1000 years. UO 2 has been doped with Pd particles [59,60] to mimic the effect of ε-phase particles (fission products forming noble metal inclusions in the fuel matrix) and with rare earth oxides [61][62][63] to mimic the effect of fission products forming oxides in the fuel matrix.…”

Section: Kinetics Of Surface Reactionsmentioning

confidence: 99%

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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“…In the case of groundwater directed to the waste in a spent nuclear fuel disposal, the environment is a dynamic redox system because of the time-dependent generation of radiolytic oxidants and reductants and the corrosion of Fe-bearing containers [1][2][3][4]. Due to the intense radiolytic field, radiation induced radiolysis products in the presence of water are considered to increase the waste form degradation rate and change radionuclide behavior.…”

Section: Introductionmentioning

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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The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2

Cited by 21 publications

References 10 publications

Radiolysis Process Model

Radiolysis Process Model

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

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

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