Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Kaija Ollila"'
Publikováno v:
Myllykylä, E, Lavonen, T, Koivula, L, Ollila, K & Siitari-Kauppi, M 2017, ' Dissolution of ThO 2 : Study of dissolution process with initial 229 Th spike ', Journal of Radioanalytical and Nuclear Chemistry, vol. 311, no. 1, pp. 225-235 . https://doi.org/10.1007/s10967-016-4991-2
The sparingly soluble ThO2 dissolution behaviour was studied under conditions that are expected to prevail in bedrock after the closure of the spent nuclear fuel disposal facility. The objective was to investigate the characteristics of initial disso
Autor:
Kerttuli Helariutta, Lauri Koivula, Marja Siitari-Kauppi, Merja Tanhua-Tyrkkö, Emmi Myllykylä, Tiina Lavonen, Kaija Ollila
Publikováno v:
Myllykylä, E, Koivula, L, Tanhua-Tyrkkö, M, Helariutta, K, Lavonen, T, Ollila, K & Siitari-Kauppi, M 2017, ' Direct alpha spectrometry for analysing leached ThO 2 pellets ', Journal of Nuclear Materials, vol. 493, pp. 69-76 . https://doi.org/10.1016/j.jnucmat.2017.06.003
The next generation application of nuclear energy has shown an interest towards ThO2 or mixed oxides fuels. However, more knowledge is needed, for example, on the microstructural and matrix dissolution behaviour of ThO2. The objective of this study w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5729426bb7ac72087b1a33f903184de6
https://cris.vtt.fi/en/publications/06760e37-29f7-4943-b411-8b45e520f17e
https://cris.vtt.fi/en/publications/06760e37-29f7-4943-b411-8b45e520f17e
Autor:
Corkhill Corkhill, Kaija Ollila, Neil C. Hyatt, Emmi Myllykylä, Tiina Lavonen, Martin C. Stennett
Publikováno v:
Myllykylä, E, Lavonen, T, Stennett, M, Corkhill, C, Ollila, K & Hyatt, N 2015, ' Solution composition and particle size effects on the dissolution and solubility of a ThO2 microstructural analogue for UO2 matrix of nuclear fuel ', Radiochimica Acta, vol. 103, no. 8, pp. 565-576 . https://doi.org/10.1515/ract-2014-2271
The objective of this study was to investigate the dissolution rate of ThO2 which was synthesised to approximate, as closely as possible, the microstructure of UO2 in a nuclear fuel matrix. The optimal sintering temperature for ThO2 pellets was found
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::03b90aecb5a8d0148b08fe80576b6cb9
https://eprints.whiterose.ac.uk/98057/3/Myllykyla_RCA__revision150115.pdf
https://eprints.whiterose.ac.uk/98057/3/Myllykyla_RCA__revision150115.pdf
Publikováno v:
Ollila, K, Myllykylä, E, Tanhua-Tyrkkö, M & Lavonen, T 2013, ' Dissolution rate of alpha-doped UO 2 in natural groundwater ', Journal of Nuclear Materials, vol. 442, no. 1-3, pp. 320-325 . https://doi.org/10.1016/j.jnucmat.2013.09.019
The objective of this work is to determine whether the presence of trace elements in natural groundwaters affects the dissolution rate of uranium dioxide in the presence of alpha radiation that causes radiolysis of water. The study is a part of the p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::73b1732a9f7ef79674477a1334bc45ba
https://cris.vtt.fi/en/publications/4e0cc566-7854-4f34-9bbb-0070aa938fe1
https://cris.vtt.fi/en/publications/4e0cc566-7854-4f34-9bbb-0070aa938fe1
Publikováno v:
Ollila, K, Olin, M & Lipponen, M 1996, ' Solubility and oxidation state of uranium under anoxic conditions (N 2 atmosphere) ', Radiochimica Acta, vol. 74, no. S1, pp. 9-13 . https://doi.org/10.1524/ract.1996.74.special-issue.9
The UO2-matrix solubility is a critical parameter for predicting the stability of spent nuclear fuel under disposal conditions. This paper presents the results obtained from the dissolution experiments of unirradiated sintered polycrystalline UO2 pel
Autor:
Kaija Ollila, Virginia Oversby
Experiments have been conducted to determine an upper limit to the dissolution rate of UO2 under reducing conditions at great depths in granitic bedrock. The aqueous phase was a dilute, synthetic groundwater that simulates fresh groundwater condition
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::da9ea90e84514f6b5216917efa8e8e99
https://doi.org/10.1557/PROC-932-76.1
https://doi.org/10.1557/PROC-932-76.1
Publikováno v:
MRS Proceedings. 294
In this study the diffusion of uranium dissolved from uranium oxide fuel was studied experimentally in compacted sodium bentonite (Wyoming bentonite MX-80). The parameters varied in the study were the density of bentonite, the salt content of the sol
Publikováno v:
MRS Proceedings. 6
The planned Swedish KBS glass corrosion investigation program comprises experiments with inactive glasses containing simulated waste, prolonged in-situ tests, the characterization of corrosion products, immiscibility studies, and corrosion experiment
Autor:
Kaija Ollila, Markus Olin
Publikováno v:
VTT Technical Research Centre of Finland-PURE
Ollila, K & Olin, M 1991, Geokemiallisen mallinnuksen soveltaminen ydinjätetutkimuksissa . in Pohjavesimallinnuksen seminaari . VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 126, pp. 21-33, Pohjavesimallinnuksen seminaari, Espoo, Finland, 9/05/91 .
Ollila, K & Olin, M 1991, Geokemiallisen mallinnuksen soveltaminen ydinjätetutkimuksissa . in Pohjavesimallinnuksen seminaari . VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 126, pp. 21-33, Pohjavesimallinnuksen seminaari, Espoo, Finland, 9/05/91 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::3e089e6ba1295418ee3f70345900ef33
https://cris.vtt.fi/en/publications/d0ed78d1-888c-43f9-b6ab-5330c8ec2b2c
https://cris.vtt.fi/en/publications/d0ed78d1-888c-43f9-b6ab-5330c8ec2b2c
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