Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides

Lemmens, Karel; González-Robles, E.; Kienzler, Bernhard; Curti, Enzo; Serrano‐Purroy, Daniel; Sureda, Rosa; Martínez-Torrents, Albert; Roth, Olivia; Slonszki, E.; Mennecart, Thierry; Günther-Leopold, Ines; Hózer, Zoltán

doi:10.1016/j.jnucmat.2016.10.048

Cited by 27 publications

(11 citation statements)

References 28 publications

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“…Although recent studies have shown a relationship between LPD and IRF [16], this work has demonstrated that other parameters such as the grain size, the pellet diameter and maybe the presence of the gap between pellets can have a sigfnicative influence in this relationship. More studies are foreseen to understand the effect of each parameter in the IRF, in order to be able to estimate the IRF of a UOx fuel from its irradiation history and morphological characteristics.…”

Section: Discussionmentioning

confidence: 54%

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Instant release fraction corrosion studies of commercial UO 2 BWR spent nuclear fuel

Martínez-Torrents

Serrano‐Purroy

Sureda

et al. 2017

Journal of Nuclear Materials

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The instant release fraction of a spent nuclear fuel is a matter of concern in the performance assessment of a deep geological repository since it increases the radiological risk. Corrosion studies of two different spent nuclear fuels were performed using bicarbonate water under oxidizing conditions to study their instant release fraction. From each fuel, cladded segments and powder samples obtained at different radial positions were used. The results were normalised using the specific surface area to permit a comparison between fuels and samples. Different radionuclide dissolution patterns were studied in terms of water contact availability and radial distribution in the spent nuclear fuel.The relationship between the results of this work and morphological parameters like the grain size or irradiation parameters such as the burn-up or the linear power density was studied in order to increase the understanding of the instant release fraction formation.

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Section: Discussionmentioning

confidence: 54%

“…Our group collaborated with the European project FIRST Nuclides [16]. One of the conclusions of this project was the determination of a trend between LPD and FGR or IRF.…”

Section: Comparison Between Fuelsmentioning

confidence: 99%

Instant release fraction corrosion studies of commercial UO 2 BWR spent nuclear fuel

Martínez-Torrents

Serrano‐Purroy

Sureda

et al. 2017

Journal of Nuclear Materials

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“…The radionuclide inventory is encapsulated in the solid uranium dioxide pellets of the assemblies, which are individually contained in canisters. After the canister is breached, the solid waste form starts to disintegrate as a result of a complex radiologic oxidation process that is approximated by a radionuclide-specific instant release fraction of a portion of the inventory [59,60] and an annual fractional degradation rate of the waste form [61]. The concentrations of radionuclides in the brine surrounding the canisters depends on the release rate, the solubility limit [11,62], and the transport processes between the waste form and the borehole, which leads to a diffusion-limited or solubility-limited sourceterm model.…”

Section: Radionuclide Inventory and Waste Mobilizationmentioning

confidence: 99%

Post-Closure Safety Analysis of Nuclear Waste Disposal in Deep Vertical Boreholes

Finsterle¹,

Muller

Grimsich

et al. 2021

Energies

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Isolation of spent nuclear fuel assemblies in deep vertical boreholes is analyzed. The main safety features of the borehole concept are related to the repository’s great depth, implying (a) long migration distances and correspondingly long travel times, allowing radionuclides to decay, (b) separation of the repository from the dynamic hydrological cycle near the land surface, (c) stable geological and hydrogeological conditions, and (d) a geochemically reducing environment. An integrated simulation model of the engineered and natural barrier systems has been developed to examine multiple scenarios of the release of radionuclides from the waste canisters, the transport through a fractured porous host rock, and the extraction of potentially contaminated drinking water from an aquifer. These generic simulations include thermal effects from both the natural geothermal gradient and the heat-generating waste, the influence of topography on regional groundwater flow, moderated by salinity stratification at depth, and the role of borehole sealing. The impact of these processes on the transport of select radionuclides is studied, which include long-lived, soluble, sorbing or highly mobile isotopes along with a decay chain of safety-relevant actinide metals. The generic analyses suggest that a deep vertical borehole repository has the potential to be a safe option for the disposal of certain waste streams, with the depth itself and the stable hydrogeological environment encountered in the emplacement zone providing inherent long-term isolation, which allows for reduced reliance on a complex engineered barrier system.

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“…36 Cl, 79 Se, 129 I, 135 Cs), immediately after the fuel comes into contact with groundwater, and 2) the release of radionuclides due to the dissolution of the UO 2 matrix, which is driven by radiolysis due to alpha radiation in aqueous solution, thus forming locally oxidizing species (e.g., H 2 O 2 ). [41][42][43] In the following, the focus will be on recent corrosion studies performed at Forschungszentrum Jülich, related to less frequently investigated SNF materials, namely, HTR fuel, research reactor fuel, and MOX fuel.…”

Section: Safety Of Spent Nuclear Fuel Disposalmentioning

confidence: 99%

“…The radionuclide release from SNF due to aqueous corrosion can be described by two components: 1) the fast (instant) release of radionuclides located in the rim and gap region and on grain boundaries (incl. 36 Cl, 79 Se, 129 I, 135 Cs), immediately after the fuel comes into contact with groundwater, and 2) the release of radionuclides due to the dissolution of the UO 2 matrix, which is driven by radiolysis due to alpha radiation in aqueous solution, thus forming locally oxidizing species (e.g., H 2 O 2 ) …”

Section: Materials Research For Nuclear Waste Management In Jülichmentioning

confidence: 99%

Research for the Safe Management of Nuclear Waste at Forschungszentrum Jülich: Materials Chemistry and Solid Solution Aspects

et al. 2020

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Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides

Cited by 27 publications

References 28 publications

Instant release fraction corrosion studies of commercial UO 2 BWR spent nuclear fuel

Instant release fraction corrosion studies of commercial UO 2 BWR spent nuclear fuel

Post-Closure Safety Analysis of Nuclear Waste Disposal in Deep Vertical Boreholes

Research for the Safe Management of Nuclear Waste at Forschungszentrum Jülich: Materials Chemistry and Solid Solution Aspects

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