Thermal hydraulic experiments for VVER reactor safety

Autor: Kouhia, Jyrki

Publikováno v: Kouhia, J 1998, Thermal hydraulic experiments for VVER reactor safety . in RETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium. Vanttola, Timo (ed) . VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 189, pp. 97-110, RETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium, Espoo, Finland, 24/11/98 . < https://publications.vtt.fi/pdf/symposiums/1998/S189.pdf >

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::736e9cdf1bd44010a72ae097421a41c5
https://cris.vtt.fi/en/publications/4aff6400-18dd-4f55-883b-7a9a964dc7d8

General description of the PACTEL test facility

Autor: Tuunanen, Jari, Kouhia, Jyrki, Purhonen, Heikki, Riikonen, Vesa, Puustinen, Markku, Semken, Scott, Partanen, Harri, Saure, Ilkka, Pylkkö, Hannu

Publikováno v: Tuunanen, J, Kouhia, J, Purhonen, H, Riikonen, V, Puustinen, M, Semken, S, Partanen, H, Saure, I & Pylkkö, H 1998, General description of the PACTEL test facility . VTT Tiedotteita-Meddelanden-Research Notes, no. 1929, VTT Technical Research Centre of Finland, Espoo . < https://publications.vtt.fi/pdf/tiedotteet/1998/T1929.pdf >

The PACTEL is a test facility designed to model the thermal-hydraulic behaviours of the Soviet-designed VVER-440 pressurized water reactors currently in use in Finland. These reactors have unique features that differ from other PWR designs. The PACTE

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::787f03581f1fda56fdaefd7fccf79b63
https://cris.vtt.fi/en/publications/cc2e7e2e-d789-4427-b0fa-51d0fb891071

Analyses of the PACTEL loss-of-feedwater experiments

Autor: Korteniemi, Virpi, Virtanen, Eero, Haapalehto, Timo, Kouhia, Jyrki

Publikováno v: Korteniemi, V, Virtanen, E, Haapalehto, T & Kouhia, J 1995, Analyses of the PACTEL loss-of-feedwater experiments . in Third International Seminar on Horizontal Steam Generators . Lappeenranta University of Technology, Lappeenranta, Lappeenrannan teknillinen korkeakoulu. Tieteellisiä julkaisuja, vol. 43, pp. 89-96, 3rd International Seminar on Horizontal Steam Generators, Lappeenranta, Finland, 18/10/94 .

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::0071bc7a92e3bd81f5061a2866d00224
https://cris.vtt.fi/en/publications/b601f14f-1d2b-4c66-a527-bb5602e5e31e

Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes

Autor: Virtanen, Eero, Haapalehto, Timo, Kouhia, Jyrki

Publikováno v: Virtanen, E, Haapalehto, T & Kouhia, J 1995, Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes . in Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7 . U.S. Nuclear Regulatory Commission, Washington, D.C., NUREG/CP, no. 0142, pp. 2806-2815, 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, Saratoga Springs, New York, United States, 10/09/95 .

Three experiments were conducted to study the behaviour of the new horizontal steam generator construction of the PACTEL test facility. In the experiments the secondary side coolant level was reduced stepwise. The experiments were calculated with two

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::574f7201ede2c3c848e1534dff21979c
https://cris.vtt.fi/en/publications/fad49363-357a-4fee-b07b-f4b64e4802d7

Analyses of PACTEL passive safety injection experiments GDE-21 through GDE-25

Autor: Tuunanen, Jari ^{a, *}, Riikonen, Vesa ^a, Kouhia, Jyrki ^a, Vihavainen, Juhani ^b

Publikováno v: In Nuclear Engineering and Design 1998 180(1):67-91