Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Riitta Kyrki-Rajamäki"'
Autor:
Virpi Kouhia, Heikki Purhonen, Vesa Riikonen, Markku Puustinen, Riitta Kyrki-Rajamäki, Juhani Vihavainen
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and
Externí odkaz:
https://doaj.org/article/9fc60548334e43e897df11b2091d9441
Publikováno v:
Daavittila, A, Hämäläinen, A & Kyrki-Rajamäki, R 2003, ' Effects of secondary circuit modeling on results of pressurized water reactor main steam line break benchmark calculations with new coupled code TRAB-3D/SMABRE ', Nuclear Technology, vol. 142, no. 2, pp. 116-123 . < http://www.ans.org/pubs/journals/nt/a_3377 >
All of the three exercises of the Organization for Economic Cooperation and Development/Nuclear Regulatory Commission pressurized water reactor main steam line break (PWR MSLB) benchmark were calculated at VTT, the Technical Research Centre of Finlan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bc728f7341b2c07a0761465404384f01
https://doi.org/10.13182/nt03-a3377
https://doi.org/10.13182/nt03-a3377
Autor:
G. Hegyi, Frank-Peter Weiss, Sören Kliem, Anitta Hämäläinen, Riitta Kyrki-Rajamäki, S. Danilin, S. Langenbuch, S. Mittag, J. Hadek
Publikováno v:
Hämäläinen, A, Kyrki-Rajamäki, R, Mittag, R, Kliem, S, Weiss, F, Langenbuch, S, Danilin, S, Hadek, J & Hegyi, G 2002, ' Validation of coupled neutron kinetic/thermal-hydraulic codes : Part 2: Analysis of a VVER-440 transient (Loviisa-1) ', Annals of Nuclear Energy, vol. 29, no. 3, pp. 255-269 . https://doi.org/10.1016/S0306-4549(01)00039-1
Several three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal-hydraulic system codes. Under the auspices of the European Union's Phare programme these codes have been validated
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6f98c734862834b9a81843eb079a641a
https://doi.org/10.1016/s0306-4549(01)00039-1
https://doi.org/10.1016/s0306-4549(01)00039-1
Autor:
S. Langenbuch, Riitta Kyrki-Rajamäki, Harri Hämäläinen, S. Danilin, D. Panayotov, G. Hegyi, A. Kuchin, Siegfried Mittag, F.-P. Weiß, Sören Kliem, J. Hadek
Publikováno v:
Mittag, R, Kliem, S, Weiss, F, Kyrki-Rajamäki, R, Hämäläinen, A, Langenbuch, S, Danilin, S, Hadek, J, Hegyi, G, Kuchin, A & Panayotov, D 2001, ' Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 1 : Analysis of a VVER-1000 transient (Balakovo-4) ', Annals of Nuclear Energy, vol. 28, no. 9, pp. 857-873 . https://doi.org/10.1016/S0306-4549(00)00095-5
Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal–hydraulic system codes. In the EU Phare project SRR1/95 these codes have been validated against real plant transients by
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ed6119ec2f00d7567632bfdfc58e585a
https://doi.org/10.1016/S0306-4549(00)00095-5
https://doi.org/10.1016/S0306-4549(00)00095-5
This book introduces readers to gas flows and heat transfer in pebble bed reactor cores. It addresses fundamental issues regarding experimental and modeling methods for complex multiphase systems, as well as relevant applications and recent research
