Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Risto Huhtanen"'
Autor:
Sunil Ganju, Takeshi Nishimura, Sergey Grigoryev, B. Gera, Anton Kanaev, M. Sharabi, Risto Huhtanen, Jongtae Kim, Luis E. Herranz, Domenico Paladino, Feng Shen, Ralf Kapulla, Berthold Schramm, Sidharth Paranjape, Avinash J. Gaikwad, Vivek A. Kale, Michele Andreani, Daqiang Yan, Rongjin Zhang, Stephan Kelm, Bai Wei
Publikováno v:
Andreani, M, Gaikwad, A J, Ganju, S, Gera, B, Grigoryev, S, Herranz, L E, Huhtanen, R, Kale, V, Kanaev, A, Kapulla, R, Kelm, S, Kim, J, Nishimura, T, Paladino, D, Paranjape, S, Schramm, B, Sharabi, M, Shen, F, Wei, B, Yan, D & Zhang, R 2019, ' Synthesis of a CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction ', Nuclear Engineering and Design, vol. 354, 110177 . https://doi.org/10.1016/j.nucengdes.2019.110177
The benchmark exercise discussed in this paper was conducted within the OECD/NEA project HYMERES. The specific experiment in the PANDA facility chosen for the present benchmark addresses the stratification erosion in a vessel where the upper region c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::beffe559898d709efd87221cc383ff0b
https://cris.vtt.fi/en/publications/30b20502-7efe-4cfa-8832-bbb0247a7465
https://cris.vtt.fi/en/publications/30b20502-7efe-4cfa-8832-bbb0247a7465
Publikováno v:
Arkoma, A, Huhtanen, R, Leppänen, J, Peltola, J & Pättikangas, T 2018, ' Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage ', Annals of Nuclear Energy, vol. 119, pp. 129–138 . https://doi.org/10.1016/j.anucene.2018.04.037
In this paper, a calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage is demonstrated. The calculation chain consists of reactor physics burnup simulation for obtaining the decay heat, Computational Fluid Dynamics
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::679cde6e2bd4fc9993a2d49359412d95
https://cris.vtt.fi/en/publications/00af13c5-f78b-4b76-a41e-bf8dcf543503
https://cris.vtt.fi/en/publications/00af13c5-f78b-4b76-a41e-bf8dcf543503
Autor:
Stephane Mimouni, Risto Huhtanen, Jianjun Xiao, Giovanni Manzini, L. Vyskocil, J. Malet, N.B. Siccama
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2015, 282, pp.44-53. ⟨10.1016/j.nucengdes.2014.12.008⟩
Malet, J, Mimouni, S, Manzini, G, Xiao, J, Vyskocil, L, Siccama, N B & Huhtanen, R 2015, ' Gas entrainment by one single French PWR spray, SARNET-2 spray benchmark ', Nuclear Engineering and Design, vol. 282, pp. 44-53 . https://doi.org/10.1016/j.nucengdes.2014.12.008
Nuclear Engineering and Design, Elsevier, 2015, 282, pp.44-53. ⟨10.1016/j.nucengdes.2014.12.008⟩
Malet, J, Mimouni, S, Manzini, G, Xiao, J, Vyskocil, L, Siccama, N B & Huhtanen, R 2015, ' Gas entrainment by one single French PWR spray, SARNET-2 spray benchmark ', Nuclear Engineering and Design, vol. 282, pp. 44-53 . https://doi.org/10.1016/j.nucengdes.2014.12.008
International audience; This paper presents a benchmark performed in the frame of the SARNET-2 EU project, dealing with momentum transfer between a real-scale PWR spray and the surrounding gas. It presents a description of the IRSN tests on the CALIS
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::12ee969d26b222637024f574d1441d61
https://doi.org/10.1016/j.nucengdes.2014.12.008
https://doi.org/10.1016/j.nucengdes.2014.12.008
Publikováno v:
Heitsch, M, Huhtanen, R, Techy, Z, Fry, C, Kostka, P, Niemi, J & Schramm, B 2010, ' CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment ', Nuclear Engineering and Design, vol. 240, no. 2, pp. 385-396 . https://doi.org/10.1016/j.nucengdes.2008.07.022
In the PHARE project “Hydrogen Management for the VVER440/213” (HU2002/000-632-04-01), CFD (Computational Fluid Dynamics) calculations using GASFLOW, FLUENT and CFX were performed for the Paks NPP (Nuclear Power Plant), modelling a defined severe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::64b78187a6b45dd274712480229c4b16
https://cris.vtt.fi/en/publications/6bd133cd-255b-418c-8400-097b72618592
https://cris.vtt.fi/en/publications/6bd133cd-255b-418c-8400-097b72618592
Publikováno v:
Manninen, M, Silde, A, Lindholm, I, Huhtanen, R & Sjövall, H 2002, ' Simulation of hydrogen deflagration and detonation in a BWR reactor building ', Nuclear Engineering and Design, vol. 211, no. 1, pp. 27-50 . https://doi.org/10.1016/S0029-5493(01)00443-5
A systematic study was carried out to investigate the hydrogen behaviour in a BWR reactor building during a severe accident. BWR core contains a large amount of Zircaloy and the containment is relatively small. Because containment leakage cannot be t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::24faaa439bd7e68066be1062d4e4f467
https://cris.vtt.fi/en/publications/9b0a9726-5cf6-46e8-a45f-ff333d13b5e4
https://cris.vtt.fi/en/publications/9b0a9726-5cf6-46e8-a45f-ff333d13b5e4
Autor:
Pauli Juutilainen, Eric Dorval, Risto Huhtanen, Jaakko Leppänen, Antti Räty, Silja Häkkinen, Toni Kaltiaisenaho, Petri Kotiluoto, Juho Peltola, Karin Rantamäki, Ville Valtavirta, Riku Tuominen, Tuomas Viitanen
Publikováno v:
VTT Technical Research Centre of Finland-PURE
Juutilainen, P, Dorval, E, Huhtanen, R, Leppänen, J, Räty, A, Häkkinen, S, Kaltiaisenaho, T, Kotiluoto, P, Peltola, J, Rantamäki, K, Valtavirta, V, Tuominen, R & Viitanen, T 2017, Nuclear criticality and safety analyses preparedness at VTT (KATVE) . in J Hämäläinen & V Suolanen (eds), SAFIR2018-The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018 : Interim Report . VTT Technical Research Centre of Finland, VTT Technology, vol. 294, pp. 162-174 .
Juutilainen, P, Dorval, E, Huhtanen, R, Leppänen, J, Räty, A, Häkkinen, S, Kaltiaisenaho, T, Kotiluoto, P, Peltola, J, Rantamäki, K, Valtavirta, V, Tuominen, R & Viitanen, T 2017, Nuclear criticality and safety analyses preparedness at VTT (KATVE) . in J Hämäläinen & V Suolanen (eds), SAFIR2018-The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018 : Interim Report . VTT Technical Research Centre of Finland, VTT Technology, vol. 294, pp. 162-174 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::193e931d4ae51c6ed6f240ad95674b9f
https://cris.vtt.fi/en/publications/739e7465-3f0e-4294-ac9c-7550249f6b49
https://cris.vtt.fi/en/publications/739e7465-3f0e-4294-ac9c-7550249f6b49
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