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Eriksen, Trygve E., Jonsson, Mats, Merino, Juan (2008) Modelling of time resolved and long contact time dissolution studies of spent nuclear fuel in 10mM carbonate solution – A comparison between two different models and experimental data. Journal of Nuclear Materials, 375 (3). 331-339 doi:10.1016/j.jnucmat.2007.12.003

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Reference TypeJournal (article/letter/editorial)
TitleModelling of time resolved and long contact time dissolution studies of spent nuclear fuel in 10mM carbonate solution – A comparison between two different models and experimental data
JournalJournal of Nuclear Materials
AuthorsEriksen, Trygve E.Author
Jonsson, MatsAuthor
Merino, JuanAuthor
Year2008 (April)Volume375
Issue3
PublisherElsevier BV
DOIdoi:10.1016/j.jnucmat.2007.12.003Search in ResearchGate
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Mindat Ref. ID4159518Long-form Identifiermindat:1:5:4159518:9
GUID0
Full ReferenceEriksen, Trygve E., Jonsson, Mats, Merino, Juan (2008) Modelling of time resolved and long contact time dissolution studies of spent nuclear fuel in 10mM carbonate solution – A comparison between two different models and experimental data. Journal of Nuclear Materials, 375 (3). 331-339 doi:10.1016/j.jnucmat.2007.12.003
Plain TextEriksen, Trygve E., Jonsson, Mats, Merino, Juan (2008) Modelling of time resolved and long contact time dissolution studies of spent nuclear fuel in 10mM carbonate solution – A comparison between two different models and experimental data. Journal of Nuclear Materials, 375 (3). 331-339 doi:10.1016/j.jnucmat.2007.12.003
In(2008, April) Journal of Nuclear Materials Vol. 375 (3) Elsevier BV

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Nielsen, Fredrik, Ekeroth, Ella, Eriksen, Trygve E., Jonsson, Mats (2008) Simulation of radiation induced dissolution of spent nuclear fuel using the steady-state approach. A comparison to experimental data. Journal of Nuclear Materials, 374 (1). 286-289 doi:10.1016/j.jnucmat.2007.08.009
Eriksen, Trygve E., Shoesmith, David W., Jonsson, Mats (2012) Radiation induced dissolution of UO2 based nuclear fuel – A critical review of predictive modelling approaches. Journal of Nuclear Materials, 420 (1). 409-423 doi:10.1016/j.jnucmat.2011.10.027
Trummer, Martin, Roth, Olivia, Jonsson, Mats (2009) H2 inhibition of radiation induced dissolution of spent nuclear fuel. Journal of Nuclear Materials, 383 (3). 226-230 doi:10.1016/j.jnucmat.2008.09.021
Trummer, Martin, Jonsson, Mats (2010) Resolving the H2 effect on radiation induced dissolution of UO2-based spent nuclear fuel. Journal of Nuclear Materials, 396 (2). 163-169 doi:10.1016/j.jnucmat.2009.10.067
Ekeroth, Ella, Jonsson, Mats, Eriksen, Trygve E, Ljungqvist, Kristina, Kovács, Sándor, Puigdomenech, Ignasi (2004) Reduction of UO22+ by H2. Journal of Nuclear Materials, 334 (1). 35-39 doi:10.1016/j.jnucmat.2004.04.324
Soderquist, Chuck, Hanson, Brady (2010) Dissolution of spent nuclear fuel in carbonate–peroxide solution. Journal of Nuclear Materials, 396 (2). 159-162 doi:10.1016/j.jnucmat.2009.11.001
Nielsen, Fredrik, Jonsson, Mats (2006) Geometrical α- and β-dose distributions and production rates of radiolysis products in water in contact with spent nuclear fuel. Journal of Nuclear Materials, 359 (1). 1-7 doi:10.1016/j.jnucmat.2006.08.001
Trummer, Martin, Nilsson, Sara, Jonsson, Mats (2008) On the effects of fission product noble metal inclusions on the kinetics of radiation induced dissolution of spent nuclear fuel. Journal of Nuclear Materials, 378 (1). 55-59 doi:10.1016/j.jnucmat.2008.04.018
Nielsen, Fredrik, Lundahl, Karin, Jonsson, Mats (2008) Simulations of H2O2 concentration profiles in the water surrounding spent nuclear fuel. Journal of Nuclear Materials, 372 (1). 32-35 doi:10.1016/j.jnucmat.2007.01.279
Nielsen, Fredrik, Jonsson, Mats (2008) Simulations of H2O2 concentration profiles in the water surrounding spent nuclear fuel taking mixed radiation fields and bulk reactions into account. Journal of Nuclear Materials, 374 (1). 281-285 doi:10.1016/j.jnucmat.2007.08.008
Barreiro Fidalgo, Alexandre, Jonsson, Mats (2019) Radiation induced dissolution of (U, Gd)O2 pellets in aqueous solution – A comparison to standard UO2 pellets. Journal of Nuclear Materials, 514. 216-223 doi:10.1016/j.jnucmat.2018.11.037
 
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