Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Merja Tanhua-Tyrkkö"'
Publikováno v:
Räty, A, Tanhua-Tyrkkö, M, Kotiluoto, P & Kekki, T 2022, ' Validation and Optimization of Activity Estimates of the FiR 1 TRIGA Research Reactor Biological Shield Concrete ', Nuclear Science and Engineering, vol. 196, no. 6, pp. 735-750 . https://doi.org/10.1080/00295639.2021.2011671
FiR 1 is a TRIGA Mark II-type research reactor in Finland. It was in operation between 1962 to 2015 and will be dismantled in 2022 to 2023. Preliminary calculations of the activities in the reactor main structures were performed in an earlier stage o
Autor:
Gabriel Lambrot, Susanna Salminen-Paatero, Celine Gautier, Wenzhong Zhang, Merja Tanhua-Tyrkkö, Elodie Laporte, Anumaija Leskinen, René Brennetot, Pascal Fichet, Jacques Bubendorff, Tommi Kekki, Antti Räty
Publikováno v:
Leskinen, A, Salminen-Paatero, S, Gautier, C, Räty, A, Tanhua-tyrkkö, M, Fichet, P, Kekki, T, Zhang, W, Bubendorff, J, Laporte, E, Lambrot, G & Brennetot, R 2020, ' Intercomparison exercise on difficult to measure radionuclides in activated steel: statistical analysis of radioanalytical results and activation calculations ', Journal of Radioanalytical and Nuclear Chemistry, vol. 324, pp. 1303-1316 . https://doi.org/10.1007/s10967-020-07181-x
This paper reports the results obtained during an intercomparison exercise for the determination of difficult to measure radionuclides in activated reactor pressure vessel (RPV) steel samples. In total, eight laboratories participated analysing 14C,
Autor:
Antti Räty, Anumaija Leskinen, Susanna Salminen-Paatero, Taneli Iso-Markku, Esa Puukko, Merja Tanhua-Tyrkkö
Publikováno v:
Leskinen, A, Salminen-Paatero, S, Räty, A, Tanhua-Tyrkkö, M, Iso-Markku, T & Puukko, E 2020, ' Determination of 14C, 55Fe, 63Ni and gamma emitters in activated RPV steel samples: a comparison between calculations and experimental analysis ', Journal of Radioanalytical and Nuclear Chemistry, vol. 323, no. 1, pp. 399-413 . https://doi.org/10.1007/s10967-019-06937-4
Determination of 14C, 55Fe, 63Ni and gamma emitters in two different types of activated reactor pressure vessel (RPV) steel samples were carried out. The gamma emitters were analysed using HPGe detectors with ISOCS and standard geometry calibrations.
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
Publikováno v:
Myllykylä, E, Tanhua-Tyrkkö, M, Bouchet, A & Tiljander, M 2013, ' Dissolution experiments of Na-and Ca-montmorillonite in groundwater simulants under anaerobic conditions ', Clay Minerals, vol. 48, no. 2, pp. 295-308 . https://doi.org/10.1180/claymin.2013.048.2.11
The effects of simulant groundwater composition, pH and temperature on the dissolution and alteration of Na- and Ca-montmorillonite have been studied. Prior to the experiments, Wyoming type Na-montmorillonite, Swy-2, was purified to decrease the amou
Publikováno v:
Itälä, A, Laitinen, M, Tanhua-Tyrkkö, M & Olin, M 2015, ' Modeling transport of water, ions, and chemical reactions in compacted bentonite: comparison among toughreact, numerrin, and comsol multiphysics ', Nuclear Technology, vol. 187, no. 2, pp. 169-174 . https://doi.org/10.13182/NT13-79
The bentonite barrier is an essential part of a safe spent fuel repository in granitic bedrock. One of the most important safety functions of bentonite buffer is to limit groundwater flow so that all mass transport takes place by diffusion. In this w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6aaf7f95701ab1e7d447325e5bc3faa3
https://cris.vtt.fi/en/publications/c56f0948-746d-4544-8a89-c4027d6c9fe2
https://cris.vtt.fi/en/publications/c56f0948-746d-4544-8a89-c4027d6c9fe2
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:
MRS Proceedings. 1475
This study aims at gaining a better understanding of the behaviour of montmorillonite in contact with different ground waters; alteration of montmorillonite and possible formation of secondary minerals. Batch experiments were conducted with purified
Autor:
Anumaija Leskinen, Merja Tanhua-Tyrkkö, Marke Susanna Salminen-Paatero, Julia Laurila, Kristian Kurhela, Xiaolin Hou, Filippa Bruzell, Tommy Suutari, Satu Kangas, Satu Rautio, Cato Christian Wendel, Marie Bourgeaux-Goget, Solveig Stordal, Joe Moussa, Ingunn Isdahl, Celine Gautier, Elodie Laporte, Margaux Giuliani, Jacques Bubendorff, Pascal Fichet
Publikováno v:
Technical University of Denmark Orbit
University of Helsinki
University of Helsinki
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::275467d8c0ff55d8c4669ad883d277fa
https://orbit.dtu.dk/en/publications/c2fe848f-c573-4173-991f-0120f8ed0c5c
https://orbit.dtu.dk/en/publications/c2fe848f-c573-4173-991f-0120f8ed0c5c
Autor:
Markus Olin, Merja Tanhua-Tyrkkö, Veli-Matti Pulkkanen, Aku-Kimmo Itälä, Kari Rasilainen, Seppälä, A., Matti Liukkonen
Publikováno v:
VTT Technical Research Centre of Finland-PURE
Olin, M, Tanhua-Tyrkkö, M, Pulkkanen, V-M, Itälä, A-K, Rasilainen, K, Seppälä, A & Liukkonen, M 2008, ' Thermo-Hydro-Mechanical-Chemical (TMHC) modeling of the bentonite barriers in final disposal of high level nuclear waste ', COMSOL Conference, Hannover, Germany, 4/11/08-6/11/08 .
Olin, M, Tanhua-Tyrkkö, M, Pulkkanen, V-M, Itälä, A-K, Rasilainen, K, Seppälä, A & Liukkonen, M 2008, ' Thermo-Hydro-Mechanical-Chemical (TMHC) modeling of the bentonite barriers in final disposal of high level nuclear waste ', COMSOL Conference, Hannover, Germany, 4/11/08-6/11/08 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::915ab24218e201774b21b7cfa0c2f9d1
https://cris.vtt.fi/en/publications/bdb90a9a-e4b5-444e-bee9-e92fd564d650
https://cris.vtt.fi/en/publications/bdb90a9a-e4b5-444e-bee9-e92fd564d650