Zobrazeno 1 - 10
of 10
pro vyhledávání: '"Kelppe, Seppo"'
Autor:
Arffman, Asko, Hämäläinen, Anitta, Ikonen, Timo, Kelppe, Seppo, Kättö, Joonas, Nieminen, Anna, Stengård, Jan-Olof, Syrjälahti, Elina, Tulkki, Ville, Tuomas, Viitanen
Publikováno v:
Arffman, A, Hämäläinen, A, Ikonen, T, Kelppe, S, Kättö, J, Nieminen, A, Stengård, J-O, Syrjälahti, E, Tulkki, V & Tuomas, V 2013, Extensive fuel modelling (PALAMA) . in SAFIR2014: The Finnish Research Programme on Nuclear Power Plant Safety 2011-2014 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Technology, no. 80, pp. 124-135 . < https://publications.vtt.fi/pdf/technology/2013/T80.pdf#page=126 >
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::b09c5fbc886406253f31dbaef7a68af3
https://cris.vtt.fi/en/publications/b7581f67-27da-4a5f-9753-bb4561c32f8e
https://cris.vtt.fi/en/publications/b7581f67-27da-4a5f-9753-bb4561c32f8e
Autor:
Kelppe, Seppo
Publikováno v:
Kelppe, S 2009, Development and validation of fuel performance codes (POKEVA) : POKEVA summary report . in SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2466, pp. 99-111 . < https://publications.vtt.fi/pdf/tiedotteet/2009/T2466.pdf >
Kelppe, S 2011, Development and Validation of Fuel Performance Codes (POKEVA) : POKEVA summary report . in SAFIR2010 : The Finnish Research Programme on Safety 2007-2010: Final Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2571, pp. 118-131 . < https://publications.vtt.fi/pdf/tiedotteet/2011/T2571.pdf >
Kelppe, S 2011, Development and Validation of Fuel Performance Codes (POKEVA) : POKEVA summary report . in SAFIR2010 : The Finnish Research Programme on Safety 2007-2010: Final Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2571, pp. 118-131 . < https://publications.vtt.fi/pdf/tiedotteet/2011/T2571.pdf >
Assessment, validation, and further development of the fuel behaviour codes in use at VTT have been continued topically, with attention to the most timely requirements. The main achievements include: (1) Development of a probabilistic procedure appli
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::daf289625834f42c6f45c7d125b9fa73
https://cris.vtt.fi/en/publications/4a72b74d-d49e-4822-8def-18b304a02a23
https://cris.vtt.fi/en/publications/4a72b74d-d49e-4822-8def-18b304a02a23
Publikováno v:
Stengård, J-O, Miettinen, J & Kelppe, S 2009, Development and validation of fuel performance codes (POKEVA) : LOCA Test Simulation with FRAPTRAN-GENFLO (POKEVA) . in SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010 : Interim Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2466, pp. 112-119 . < https://publications.vtt.fi/pdf/tiedotteet/2009/T2466.pdf >
In assuring reactor safety with increasing target burnups, fuel behaviour in postulated accident conditions is receiving high attention. Within the OECD Halden Project in Norway, a programme of integral reactor tests in closely simulated light-water
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::5fa87420d6402774fa49e707157f3e54
https://cris.vtt.fi/en/publications/9aa34b98-ba52-4728-80ff-0ce738e22f0d
https://cris.vtt.fi/en/publications/9aa34b98-ba52-4728-80ff-0ce738e22f0d
Autor:
Kelppe, Seppo
Publikováno v:
Kelppe, S 2006, KORU summary report . in SAFIR: The Finnish Research Programme on Nuclear Power Plant Safety 2003-2006 : Final Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2363, pp. 60-68 . < https://publications.vtt.fi/pdf/tiedotteet/2006/T2363.pdf >
The modelling in fuel behaviour codes that are in use at VTT has been subject to extensive upgrading in a number of respects. Major achievements include: 1) Streamlining of the coupling of the advanced thermal hydraulic module GENFLO with successive
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::e7bf846dadba7e246708d7e24ad8710c
https://cris.vtt.fi/en/publications/4766d240-9a01-41fa-bea2-dee4ad356a83
https://cris.vtt.fi/en/publications/4766d240-9a01-41fa-bea2-dee4ad356a83
Publikováno v:
Kelppe, S, Kyrki-Rajamäki, R, Räty, H & Valtonen, K 2003, Coupled modelling of fuel behaviour, neutronics, and thermal hydraulics in safety assessments at high burnup . in Proceedings of the Topical Meeting on RIA . OECD NEA Committee on the Safety of Nuclear Installations, Paris, NEA Committee on the Safety of Nuclear Installations. Report, no. NEA/CSNI/R(2003)8/VOL1, pp. 73-86, 2nd OECD/NEA/CSNI Topical Meeting on Reactivity Initiated Accidents Safety Criteria, Aix-en-Provence, France, 14/05/02 . < https://www.oecd-nea.org/nsd/docs/2003/csni-r2003-8-vol1.pdf >
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::63ed15ba93e302eeab4510a742eaab07
https://cris.vtt.fi/en/publications/ec97eeb7-4eea-4ea6-8e29-3d125d8e03d7
https://cris.vtt.fi/en/publications/ec97eeb7-4eea-4ea6-8e29-3d125d8e03d7
Autor:
Kelppe, Seppo
Publikováno v:
Kelppe, S 2002, Transient behaviour of high burnup fuel (KOTO) : KOTO summary report . in FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002 : Final Report . VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita-Research Notes, no. 2164, pp. 95-103 . < https://publications.vtt.fi/pdf/tiedotteet/2002/T2164.pdf >
There is a clear economic incentive for the industry to continue the trend of pursuing higher fuel discharge burnups, which translates into higher neutron fluences, often together with longer residence times in the reactor. Testing and irradiation ex
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::c3417fa97d5f80dfb241e6de070ee107
https://cris.vtt.fi/en/publications/6ea0185c-81c8-4691-a712-18a14b4cd308
https://cris.vtt.fi/en/publications/6ea0185c-81c8-4691-a712-18a14b4cd308
Publikováno v:
Ranta-Puska, K, Kelppe, S & Pihlatie, M 2000, Recent safety related studies in VTT : 1. Probabilistic assessment of in-reactor fuel conditions . in E Virtanen (ed.), Proceedings of 3rd Finnish-French colloquium on nuclear power plant safety . Lappeenranta University of Technology, Acta Universitatis Lappeenrantaensis, vol. 100, pp. 20-25, 3rd Finnish-French colloquium on nuclear power plant safety, Lappeenranta, Finland, 27/06/00 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::15ffb17dd4798c17d794f45b835f7823
https://cris.vtt.fi/en/publications/92731d3d-507e-4310-aea0-177ef5a2ce77
https://cris.vtt.fi/en/publications/92731d3d-507e-4310-aea0-177ef5a2ce77
Autor:
Kelppe, Seppo, Ranta-Puska, Kari
Publikováno v:
Kelppe, S & Ranta-Puska, K 1998, Probabilistic assessments of fuel performance . 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. 37-46, 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::3186c3adb25066df17bf0885422ba8d1
https://cris.vtt.fi/en/publications/61e4ca60-a876-445c-8923-f295de5d36cd
https://cris.vtt.fi/en/publications/61e4ca60-a876-445c-8923-f295de5d36cd
Publikováno v:
Lassmann, K, Kelppe, S & Mattila, L 1978, Comparative evaluation of the steady state fuel rod thermal behaviour code CAPCON-THERMAL-2 and the integral fuel for performance code URANUS . Valtion teknillinen tutkimuskeskus: Ydinvoimatekniikan laboratorio. Tiedonanto, no. 34, VTT Technical Research Centre of Finland, Helsinki .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::b9978c89827b4301f84f9d38873351f2
https://cris.vtt.fi/en/publications/8ccc1935-2154-4be6-b263-adace0c43359
https://cris.vtt.fi/en/publications/8ccc1935-2154-4be6-b263-adace0c43359
Autor:
Kelppe, Seppo, Mattila, Lasse, Puska, Eija-Karita, Ranta-Puska, Kari, Sairanen, Risto, Stengård, Jan-Olof
Publikováno v:
Kelppe, S, Mattila, L, Puska, E-K, Ranta-Puska, K, Sairanen, R & Stengård, J-O 1989, Ydinpolttoaineen käyttäytymisen ja suorituskyvyn arviointi . Valtion teknillinen tutkimuskeskus. Tiedotteita, no. 957, VTT Technical Research Centre of Finland, Espoo .
Ydinreaktorin polttoainesauvojen lämpöteknisen ja mekaanisen käyttäytymisen arviointimenetelmät ovat merkittävällä sijalla varmistettaessa ydinvoimalaitoksen käyttöturvallisuutta ja suunnittelun perustana olevien onnettomuustilanteiden hall
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::0ba735f445500c593f3565a35b64f329
https://cris.vtt.fi/en/publications/89466f15-9011-424e-bffb-88793e700095
https://cris.vtt.fi/en/publications/89466f15-9011-424e-bffb-88793e700095