Zobrazeno 1 - 10
of 28
pro vyhledávání: '"Pelli, Reijo"'
Autor:
Pelli, Reijo
Publikováno v:
Pelli, R 2000, Uusia korjaus-ja parannusmenetelmiä ydinvoimalaitosmateriaaleille . VTT Valmistustekniikka. Tutkimusraportti, no. BVAL62-001050, VTT Technical Research Centre of Finland, Espoo .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::7a928f461a84bf4676caaff54f481012
https://cris.vtt.fi/en/publications/3444e1ac-75ad-4e72-b223-dd7e645aa01e
https://cris.vtt.fi/en/publications/3444e1ac-75ad-4e72-b223-dd7e645aa01e
Autor:
Bhandari, S., Cueto-Felgueroso, C., Grebner, H., Horsten, M., Keim, E., Pelli, Reijo, Popov, A., Sievers, Jurgen
Publikováno v:
Bhandari, S, Cueto-Felgueroso, C, Grebner, H, Horsten, M, Keim, E, Pelli, R, Popov, A & Sievers, J 2000, Evaluation of the potential role of cladding in RPV safety analysis . in S K Bhandari, K K Yoon & D Moinereau (eds), Severe accidents and other topics in the RPV design 2000 . American Society of Mechanical Engineers (ASME), New York, American Society of Mechanical Engineers. Pressure Vessels and Piping Division. Publication PVP, vol. 403, pp. 223-232, ASME 2000 Pressure Vessels and Piping Conference, Seattle, Washington, United States, 23/07/00 .
Although the major objective in the deposition of cladding on the inner surface of an LWR pressure vessel is to prevent the corrosion of the base material, the presence of cladding leads to the consideration of its role in the mechanical analysis of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::1bec6a7a5238b19466a319e7de4193a1
https://cris.vtt.fi/en/publications/386fcff6-842f-4f17-9e76-d8fb411ecea6
https://cris.vtt.fi/en/publications/386fcff6-842f-4f17-9e76-d8fb411ecea6
Publikováno v:
Planman, T, Pelli, R & Törrönen, K 1995, Irradiation embrittlement mitigation . EU Publications, no. EUR 16072 EN, AMES Report, no. 1, European Commission EC, Luxembourg . < https://op.europa.eu/en/publication-detail/-/publication/1fb872d3-afc1-11e7-837e-01aa75ed71a1 >
Neutron irradiation affects the material properties, and hence the structural integrity, of reactor pressure vessels in nuclear power plants. Mitigation of irradiation damage is one of the major issues within nuclear plant life management. An overvie
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::9fea9cb51fab916817f257dede0122d8
https://cris.vtt.fi/en/publications/555c01b5-088b-4959-b7b5-3bcdbfa1993f
https://cris.vtt.fi/en/publications/555c01b5-088b-4959-b7b5-3bcdbfa1993f
Autor:
Rintamaa, Rauno, Karjalainen-Roikonen, Päivi, Aaltonen, Pertti, Kauppinen, Pentti, Pelli, Reijo, Keinänen, Heikki, Talja, Heli, Planman, Tapio, Valo, Matti, Nevalainen, Markku, Wallin, Kim
Publikováno v:
Rintamaa, R, Karjalainen-Roikonen, P, Aaltonen, P, Kauppinen, P, Pelli, R, Keinänen, H, Talja, H, Planman, T, Valo, M, Nevalainen, M & Wallin, K 1995, Overview of some recent results of the VTT's research programme on assuring nuclear power plant structural safety . VALB, no. 102, VTT Technical Research Centre of Finland .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::38bfed964836f536c3e6d527d671b9ee
https://cris.vtt.fi/en/publications/8df61bf6-8233-41ad-ad6b-31c42084ae20
https://cris.vtt.fi/en/publications/8df61bf6-8233-41ad-ad6b-31c42084ae20
Publikováno v:
Pelli, R, Planman, T, Rintamaa, R, Karzov, G & Timofeev, B 1995, Simulation of irradiation embrittlement of welded pressure vessel material corresponding to the end of VVER-440 reactor service life . in IAEA Specialists' Meeting on Irradiation Embrittlement and Mitigation . vol. II, International Atomic Energy Agency IAEA, Vienna, International Working Group on Life Management of Nuclear Power Plants, no. IAEA IWG-LMNPP-95/5, IAEA Specialists' Meeting on Irradiation Embrittlement and Mitigation, Espoo, Finland, 23/10/95 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::14c58d8e3fa32054b6830f7be7159614
https://cris.vtt.fi/en/publications/4847ff5e-4088-4450-8802-10945242cad9
https://cris.vtt.fi/en/publications/4847ff5e-4088-4450-8802-10945242cad9
Publikováno v:
Törrönen, K, Pelli, R, Planman, T & Valo, M 1993, Irradiation embrittlement mitigation . in Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing . IAEA/NEA, Paris, INIS Report, no. NEA-CSNI-R--94-1, IAEA Conference Proceedings, no. IWG-LMNPP 93/03, pp. 351-379, 1993 Specialists' Meeting on Irradiation Embrittlement and Optimization of Annealing, Paris, France, 20/09/93 . < https://inis.iaea.org/search/search.aspx?orig_q=RN:28029677 >
Mitigation methods for reducing the irradiation damage on pressure vessel materials are reviewed: load leakage loading schemes are commonly used in PWRs to mitigate reactor pressure vessel embrittlement; dummy assemblies have been applied in WWER 440
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::fbb99be4b27a0f52567fbc04dab8de1e
https://cris.vtt.fi/en/publications/9a901f17-70bc-4d7a-9dfd-08f7fad64aee
https://cris.vtt.fi/en/publications/9a901f17-70bc-4d7a-9dfd-08f7fad64aee
Publikováno v:
Pelli, R, Kemppainen, M & Törrönen, K 1979, Reactor pressure vessel steels ASTM A533B and A508 Cl.2 : Tensile test results . Valtion teknillinen tutkimuskeskus. Metallilaboratorio. Tiedonanto, no. 60, VTT Technical Research Centre of Finland, Espoo .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::004eea31627bc1d9941895f71758e87e
https://cris.vtt.fi/en/publications/4e7e69b4-d045-4009-80e3-2f63e13423e0
https://cris.vtt.fi/en/publications/4e7e69b4-d045-4009-80e3-2f63e13423e0
Publikováno v:
Salonen, S, Pelli, R & Hakala, J 1979, Hiiliteräksestä kuumamuokkaamalla valmistettavien muotokappaleiden valmistusmenetelmät ja ominaisuudet : Kirjallisuusselvitys . Valtion teknillinen tutkimuskeskus. Metallilaboratorio. Tiedonanto, no. 51, VTT Technical Research Centre of Finland, Espoo .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::88d0a4027aa732370f5521585185b39a
https://cris.vtt.fi/en/publications/329fb035-f9b1-453d-8852-4e68a6d452d8
https://cris.vtt.fi/en/publications/329fb035-f9b1-453d-8852-4e68a6d452d8
Publikováno v:
Pelli, R, Kemppainen, M & Törrönen, K 1978, Reactor pressure vessel steels ASTM A533B and A508 cl. 2 : Heat treatment programmes . Valtion teknillinen tutkimuskeskus. Metallilaboratorio. Tiedonanto, no. 36, VTT Technical Research Centre of Finland, Espoo .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::9f177d0c226f5b9961a77e67bd2f2d3c
https://cris.vtt.fi/en/publications/816287f9-2b98-485f-b9f3-92dea30f6fb3
https://cris.vtt.fi/en/publications/816287f9-2b98-485f-b9f3-92dea30f6fb3
Autor:
Pelli, Reijo
Publikováno v:
Pelli, R 1986, ' Ydinvoimalaitosten materiaalivauriot ', ATS Ydintekniikka, no. 1, pp. 16-17 .
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=355e65625b88::f6e3fdbfa8e3a4fd4496d79caddbcdf4
https://cris.vtt.fi/en/publications/2bde2ebf-96bd-4581-b987-d87d5445acab
https://cris.vtt.fi/en/publications/2bde2ebf-96bd-4581-b987-d87d5445acab