Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: Effect of high burn-up structure and leaching solution composition

Serrano‐Purroy, Daniel; Clarens, F.; González-Robles, E.; Glatz, Jean‐Paul; Wegen, D.; Pablo, Joan de; Casas, I.; Giménez, Javier; Martínez-Esparza, A.

doi:10.1016/j.jnucmat.2012.04.036

Cited by 34 publications

(13 citation statements)

References 30 publications

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“…where m i,aq is the mass of element/nuclide i in the aqueous phase in g, and m i,sample is the mass of element/nuclide i in sample A (or sample B) in g. In this study, m i,aq was calculated by multiplying the element/ nuclide concentration by the volume of the solution, and m i,sample was calculated by ORIGEN2 [15]. Fractional release normalised to uranium for an element/nuclide i (FNU i ) [16] was obtained by the following equation:…”

Section: Leaching Experimentsmentioning

confidence: 99%

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Leaching behavior of radionuclides from samples prepared from spent fuel rod comparable to core debris in the 1F NPS

Onishi

Maeda

Katsuyama

2020

Journal of Nuclear Science and Technology

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To investigate the leaching behavior of radioactive nuclides in leaching samples comparable to core debris (partially molten ZrO 2 /UO 2 between fuel rods) in the Fukushima Daiichi Nuclear Power Station (1 F NPS), the concentration of radionuclides in the leaching solution was measured. The leaching behaviors of actinides (U, Pu, and Np) and Cs from the samples were similar to those from spent fuel. As predicted from the current thermodynamic database, the leaching of U and Pu depends on the pH in the cooling water of the core debris. However, if Mo and Tc are surrounded by zircaloy in the core debris, their leaching amount may increase by one order of magnitude than those from spent fuel.

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Section: Leaching Experimentsmentioning

confidence: 99%

“…16. FNU i of molybdeun-97, technetium-99, ruthenium-102, and rhodium-103 (FNU i : Fractional release normalised to uranium for an element/nuclide i).…”

mentioning

confidence: 99%

Leaching behavior of radionuclides from samples prepared from spent fuel rod comparable to core debris in the 1F NPS

Onishi

Maeda

Katsuyama

2020

Journal of Nuclear Science and Technology

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“…On the other hand, the range of cesium and strontium concentrations studied in this work comprises the actual cesium and strontium concentrations released from SNF in leaching experiments: 10 -10 −5 mol dm −3 for strontium [30][31][32][33]. At such ranges of concentration, experimental data obtained in this work indicate that sorption is favoured for both radionuclides.…”

Section: Potential Impact Of the Formation Of Uranophane In A Hlnwrmentioning

confidence: 97%

Retention of cesium and strontium by uranophane, Ca(UO2)2(SiO3OH)2·5H2O

Espriu-Gascon

Giménez

Casas

et al. 2018

Journal of Hazardous Materials

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This work determines the capacity of uranophane, one of the long-term uranyl secondary solid phases formed on the spent nuclear fuel (SNF), to retain radionuclides (cesium and strontium) released during the dissolution of the SNF. Sorption was fast in both cases, and uranophane had a high sorption capacity for both radionuclides (maximum sorption capacities of 1.53·10 mol m for cesium and 3.45·10 mol m for strontium). The high sorption capacity of uranophane highlights the importance of the formation of uranyl silicates as secondary phases during the SNF dissolution, especially in retaining the release of radionuclides not retarded by other mechanisms such as precipitation.

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“…To ensure long-term safety of spent nuclear fuel, deep geologic repository is the most accepted solution by the scientific community [1]. Within this concept, the spent fuel matrix is the first barrier in case of a canister breakage [2]. Once the groundwater enters into contact with the spent fuel, the radionuclides will be released into the geosphere [2].…”

Section: Introductionmentioning

confidence: 99%

“…Within this concept, the spent fuel matrix is the first barrier in case of a canister breakage [2]. Once the groundwater enters into contact with the spent fuel, the radionuclides will be released into the geosphere [2]. The Instant Release Fraction (IRF) comprises the radionuclides segregated during the irradiation and with faster dissolution rates than the matrix and constitutes one of the main sources of radiological risks for the geological repository [3].…”

Section: Introductionmentioning

confidence: 99%

An Automated SeaFAST ICP-DRC-MS Method for the Determination of 90Sr in Spent Nuclear Fuel Leachates

et al. 2020

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To reduce uncertainties in determining the source term and evolving condition of spent nuclear fuel is fundamental to the safety assessment. ß-emitting nuclides pose a challenging task for reliable, quantitative determination because both radiometric and mass spectrometric methodologies require prior chemical purification for the removal of interfering activity and isobars, respectively. A method for the determination of 90Sr at trace levels in nuclear spent fuel leachate samples without sophisticated and time-consuming procedures has been established. The analytical approach uses a commercially available automated pre-concentration device (SeaFAST) coupled to an ICP-DRC-MS. The method shows good performances with regard to reproducibility, precision, and LOD reducing the total time of analysis for each sample to 12.5 min. The comparison between the developed method and the classical radiochemical method shows a good agreement when taking into account the associated uncertainties.

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Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: Effect of high burn-up structure and leaching solution composition

Cited by 34 publications

References 30 publications

Leaching behavior of radionuclides from samples prepared from spent fuel rod comparable to core debris in the 1F NPS

Leaching behavior of radionuclides from samples prepared from spent fuel rod comparable to core debris in the 1F NPS

Retention of cesium and strontium by uranophane, Ca(UO2)2(SiO3OH)2·5H2O

An Automated SeaFAST ICP-DRC-MS Method for the Determination of 90Sr in Spent Nuclear Fuel Leachates

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