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Martínez-Torrents, A., Serrano-Purroy, D., Casas, I., De Pablo, J. (2018) Influence of the interpellet space to the Instant Release Fraction determination of a commercial UO2 Boiling Water Reactor Spent Nuclear Fuel. Journal of Nuclear Materials, 499. 9-17 doi:10.1016/j.jnucmat.2017.10.064

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Reference TypeJournal (article/letter/editorial)
TitleInfluence of the interpellet space to the Instant Release Fraction determination of a commercial UO2 Boiling Water Reactor Spent Nuclear Fuel
JournalJournal of Nuclear Materials
AuthorsMartínez-Torrents, A.Author
Serrano-Purroy, D.Author
Casas, I.Author
De Pablo, J.Author
Year2018 (February)Volume499
PublisherElsevier BV
DOIdoi:10.1016/j.jnucmat.2017.10.064Search in ResearchGate
Generate Citation Formats
Mindat Ref. ID4167265Long-form Identifiermindat:1:5:4167265:5
GUID0
Full ReferenceMartínez-Torrents, A., Serrano-Purroy, D., Casas, I., De Pablo, J. (2018) Influence of the interpellet space to the Instant Release Fraction determination of a commercial UO2 Boiling Water Reactor Spent Nuclear Fuel. Journal of Nuclear Materials, 499. 9-17 doi:10.1016/j.jnucmat.2017.10.064
Plain TextMartínez-Torrents, A., Serrano-Purroy, D., Casas, I., De Pablo, J. (2018) Influence of the interpellet space to the Instant Release Fraction determination of a commercial UO2 Boiling Water Reactor Spent Nuclear Fuel. Journal of Nuclear Materials, 499. 9-17 doi:10.1016/j.jnucmat.2017.10.064
In(2018) Journal of Nuclear Materials Vol. 499. Elsevier BV

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Martínez-Torrents, Albert, Serrano-Purroy, Daniel, Sureda, Rosa, Casas, Ignasi, de Pablo, Joan (2017) Instant release fraction corrosion studies of commercial UO 2 BWR spent nuclear fuel. Journal of Nuclear Materials, 488. 302-313 doi:10.1016/j.jnucmat.2017.03.022
Espriu-Gascon, Alexandra, Martínez-Torrents, Albert, Serrano-Purroy, Daniel, Giménez, Javier, de Pablo, Joan, Casas, Ignasi (2020) Contribution of phases segregated from the UO2 matrix to the release of radionuclides from spent nuclear fuel and duration of the Instant Release Fraction (IRF). Journal of Nuclear Materials, 532. 152066pp. doi:10.1016/j.jnucmat.2020.152066
Serrano-Purroy, D., Clarens, F., González-Robles, E., Glatz, J.P., Wegen, D.H., de Pablo, J., Casas, I., Giménez, J., Martínez-Esparza, A. (2012) Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: Effect of high burn-up structure and leaching solution composition. Journal of Nuclear Materials, 427 (1). 249-258 doi:10.1016/j.jnucmat.2012.04.036
González-Robles, E., Serrano-Purroy, D., Sureda, R., Casas, I., de Pablo, J. (2015) Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction. Journal of Nuclear Materials, 465. 63-70 doi:10.1016/j.jnucmat.2015.05.012
Serrano-Purroy, D., Casas, I., González-Robles, E., Glatz, J.P., Wegen, D.H., Clarens, F., Giménez, J., de Pablo, J., Martínez-Esparza, A. (2013) Dynamic leaching studies of 48MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions. Journal of Nuclear Materials, 434 (1). 451-460 doi:10.1016/j.jnucmat.2011.03.020
Martínez-Torrents, Albert, Purroy, Daniel Serrano, Kokinda, Jakub, Pérez, Luis Iglesias, Clarens, Frederic, Giménez, Javier, de Pablo, Joan (2024) Release of Cs, Sr and Rb from two high–burnup spent nuclear fuels: Effect of the dishing and the internal grain boundaries. Journal of Nuclear Materials, 598. 155162 doi:10.1016/j.jnucmat.2024.155162
Lemmens, K., González-Robles, E., Kienzler, B., Curti, E., Serrano-Purroy, D., Sureda, R., Martínez-Torrents, A., Roth, O., Slonszki, E., Mennecart, T., Günther-Leopold, I., Hózer, Z. (2017) Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides. Journal of Nuclear Materials, 484. 307-323 doi:10.1016/j.jnucmat.2016.10.048
Giménez, J., Clarens, F., Casas, I., Rovira, M., de Pablo, J., Bruno, J. (2005) Oxidation and dissolution of UO2 in bicarbonate media: Implications for the spent nuclear fuel oxidative dissolution mechanism. Journal of Nuclear Materials, 345 (2). 232-238 doi:10.1016/j.jnucmat.2005.06.003
Merino, J., Cera, E., Bruno, J., Quiñones, J., Casas, I., Clarens, F., Giménez, J., de Pablo, J., Rovira, M., Martínez-Esparza, A. (2005) Radiolytic modelling of spent fuel oxidative dissolution mechanism. Calibration against UO2 dynamic leaching experiments. Journal of Nuclear Materials, 346 (1). 40-47 doi:10.1016/j.jnucmat.2005.05.019
de Pablo, J., Casas, I., Giménez, J., Martí, V., Torrero, M.E. (1996) Solid surface evolution model to predict uranium release from unirradiated UO2 and nuclear spent fuel dissolution under oxidizing conditions. Journal of Nuclear Materials, 232 (2). 138-145 doi:10.1016/s0022-3115(96)00439-4
Johnson, Lawrence, Ferry, Cécile, Poinssot, Christophe, Lovera, Patrick (2005) Spent fuel radionuclide source-term model for assessing spent fuel performance in geological disposal. Part I: Assessment of the instant release fraction. Journal of Nuclear Materials, 346 (1). 56-65 doi:10.1016/j.jnucmat.2005.04.071
 
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