المؤلفون: Arffman, Asko, Hämäläinen, Anitta, Ikonen, Timo, Kelppe, Seppo, Kättö, Joonas, Nieminen, Anna, Stengård, Jan-Olof, Syrjälahti, Elina, Tulkki, Ville, Tuomas, Viitanen

المصدر: 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 >

URL الوصول: https://explore.openaire.eu/search/publication?articleId=355e65625b88::b09c5fbc886406253f31dbaef7a68af3
https://cris.vtt.fi/en/publications/b7581f67-27da-4a5f-9753-bb4561c32f8e

المؤلفون: Kelppe, Seppo

المصدر: 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 >

URL الوصول: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::daf289625834f42c6f45c7d125b9fa73
https://cris.vtt.fi/en/publications/4a72b74d-d49e-4822-8def-18b304a02a23

المؤلفون: Stengård, Jan-Olof, Miettinen, Jaakko, Kelppe, Seppo

المصدر: 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 >

URL الوصول: https://explore.openaire.eu/search/publication?articleId=355e65625b88::5fa87420d6402774fa49e707157f3e54
https://cris.vtt.fi/en/publications/9aa34b98-ba52-4728-80ff-0ce738e22f0d

المؤلفون: Kelppe, Seppo

المصدر: 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 >

URL الوصول: https://explore.openaire.eu/search/publication?articleId=355e65625b88::e7bf846dadba7e246708d7e24ad8710c
https://cris.vtt.fi/en/publications/4766d240-9a01-41fa-bea2-dee4ad356a83

المؤلفون: Kelppe, Seppo, Kyrki-Rajamäki, Riitta, Räty, Hanna, Valtonen, K.

المصدر: 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 >

مصطلحات موضوعية: nuclear fuel, reactor dynamics, thermal hydraulics

URL الوصول: https://explore.openaire.eu/search/publication?articleId=355e65625b88::63ed15ba93e302eeab4510a742eaab07
https://cris.vtt.fi/en/publications/ec97eeb7-4eea-4ea6-8e29-3d125d8e03d7

المؤلفون: Kelppe, Seppo

المصدر: 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 >

URL الوصول: https://explore.openaire.eu/search/publication?articleId=355e65625b88::c3417fa97d5f80dfb241e6de070ee107
https://cris.vtt.fi/en/publications/6ea0185c-81c8-4691-a712-18a14b4cd308

المؤلفون: Ranta-Puska, Kari, Kelppe, Seppo, Pihlatie, Mikko

المساهمون: Virtanen, Eero

المصدر: 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 .

URL الوصول: https://explore.openaire.eu/search/publication?articleId=355e65625b88::15ffb17dd4798c17d794f45b835f7823
https://cris.vtt.fi/en/publications/92731d3d-507e-4310-aea0-177ef5a2ce77

المؤلفون: Kelppe, Seppo, Ranta-Puska, Kari

المصدر: 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 >

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https://cris.vtt.fi/en/publications/61e4ca60-a876-445c-8923-f295de5d36cd

المؤلفون: Lassmann, K., Kelppe, Seppo, Mattila, Lasse

المصدر: 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 .

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https://cris.vtt.fi/en/publications/8ccc1935-2154-4be6-b263-adace0c43359

المؤلفون: Kelppe, Seppo, Mattila, Lasse, Puska, Eija-Karita, Ranta-Puska, Kari, Sairanen, Risto, Stengård, Jan-Olof

المصدر: 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 .

مصطلحات موضوعية: nuclear fuel element, thermal behavior, mechanical properties

URL الوصول: https://explore.openaire.eu/search/publication?articleId=355e65625b88::0ba735f445500c593f3565a35b64f329
https://cris.vtt.fi/en/publications/89466f15-9011-424e-bffb-88793e700095