Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Vesa Riikonen"'
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:
Nuclear Engineering and Design. 332:111-118
Noncondensable gases, if present in the reactor cooling system, affect the coolability of the nuclear reactor core. In Loss-Of-Coolant Accidents (LOCA), nitrogen from hydroaccumulators will enter the reactor systems, and can temporarily alter the wat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7c40385faf2e03dfc87c1254e6e164e3
https://doi.org/10.1016/j.nucengdes.2018.03.027
https://doi.org/10.1016/j.nucengdes.2018.03.027
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2010 (2010)
This paper summarizes the analysis results of three PACTEL experiments, carried out with the advanced thermal-hydraulic system computer CATHARE 2 code as a part of the second work package WP2 (analytical work) of the EC project “Improved Accident M
Externí odkaz:
https://doaj.org/article/0aebfec15aa6478f841943cb90087ce9
Publikováno v:
Nuclear Engineering and Design. 383:111417
The PASI test facility has been designed and constructed at LUT University for the thermal–hydraulic studies of an open-loop passive containment heat removal system for nuclear reactors. The PASI facility consists of a pressure vessel that simulate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::57f04732d6e3ff39cb1e2064d6cfe20b
https://doi.org/10.1016/j.nucengdes.2021.111417
https://doi.org/10.1016/j.nucengdes.2021.111417
Publikováno v:
Hovi, V, Pättikangas, T & Riikonen, V 2016, ' Coupled one-dimensional and CFD models for the simulation of steam generators ', Nuclear Engineering and Design, vol. 310, pp. 93-111 . https://doi.org/10.1016/j.nucengdes.2016.09.023
A computational procedure suitable for modeling both vertical and horizontal steam generators is presented. The procedure consists of a one-dimensional model for the whole steam generator and a CFD model for the secondary side. The three-dimensional
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::de6fd96bbfe7aca793e79d1b909ec740
https://cris.vtt.fi/en/publications/a13f7c2c-f95c-4f6a-8341-64e45d2c36f9
https://cris.vtt.fi/en/publications/a13f7c2c-f95c-4f6a-8341-64e45d2c36f9
Publikováno v:
Annals of Nuclear Energy. 85:47-57
Water seal formation in the loop seal in pressurized water reactors can occur during a small or intermediate break loss-of-coolant accident, causing temporary fuel overheating. Quantification of the accuracy of overheating prediction is of interest i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::19a64777585ffa185939a190886dacaf
https://doi.org/10.1016/j.anucene.2015.04.036
https://doi.org/10.1016/j.anucene.2015.04.036
Publikováno v:
Nuclear Engineering and Design. 353:110288
The hydroaccumulators in pressurized water reactors can inject nitrogen into the reactor system. In the primary system, nitrogen affects core cooling and accident management, both adversely and beneficially. The PWR PACTEL experiment NCG-13 have show
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6b6774dd57a6effe737dc3a7b439c59b
https://doi.org/10.1016/j.nucengdes.2019.110288
https://doi.org/10.1016/j.nucengdes.2019.110288
Publikováno v:
Annals of Nuclear Energy. 37:1494-1501
This paper describes the modeling of horizontal steam generator with the TRACE code and calculation results of a loss-of-feedwater (LOF-10) experiment at the PACTEL facility. Parallel Channel Test Loop (PACTEL) is an integral test facility for a VVER
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8cf903321cc24be0c1bfcedcd60feb44
https://doi.org/10.1016/j.anucene.2010.06.013
https://doi.org/10.1016/j.anucene.2010.06.013
Publikováno v:
Tuunanen, J, Riikonen, V, Kouhia, J & Vihavainen, J 1998, ' Analyses of PACTEL passive safety injection experiments GDE-21 through GDE-25 ', Nuclear Engineering and Design, vol. 180, no. 1, pp. 67-91 . https://doi.org/10.1016/S0029-5493(97)00306-3
In advanced light water reactors (ALWR), gravity-driven passive safety injection systems (PSIS) replace pump-driven emergency core cooling systems. PSISs often rely on small density differences and driving forces for natural circulation. In a typical
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::63918ca00882eaa882b901b435980867
https://doi.org/10.1016/s0029-5493(97)00306-3
https://doi.org/10.1016/s0029-5493(97)00306-3
Autor:
Jozsef Banati, M. Cherubini, Lauri Peltokorpi, Heikki Purhonen, Pavel Kral, Virpi Kouhia, Ismo Karppinen, Sebastian Weber, Francesco Saverio D'Auria, Henrique Austregesilo, Otso-Pekka Kauppinen, Pasi Inkinen, Vesa Riikonen, Joanna Peltonen
Publikováno v:
Kouhia, V, Riikonen, V, Kauppinen, O-P, Purhonen, H, Austregesilo, H, Bánáti, J, Cherubini, M, d'Auria, F, Inkinen, P, Karppinen, I, Kral, P, Peltokorpi, L, Peltonen, J & Weber, S 2013, ' Benchmark exercise on SBLOCA experiment of PWR PACTEL facility ', Annals of Nuclear Energy, vol. 59, pp. 149-156 . https://doi.org/10.1016/j.anucene.2013.04.004
The PWR PACTEL benchmark exercise was organized in Lappeenranta, Finland by Lappeenranta University of Technology. The benchmark consisted of two phases, i.e. a blind and an open calculation task. Seven organizations from the Czech Republic, Germany,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::67b0b5ba3f1fda271f7b0e6b3757c5dc
https://cris.vtt.fi/en/publications/7e54009e-e772-46b4-9059-968d78ac8c81
https://cris.vtt.fi/en/publications/7e54009e-e772-46b4-9059-968d78ac8c81
