Výsledky vyhledávání - "Rauno Rintamaa"

Applicability of miniature size bend specimens to determine the master curve reference temperature T0

Autor: Rauno Rintamaa, Matti Valo, Tapio Planman, Kim Wallin

Publikováno v: Wallin, K, Planman, T, Valo, M & Rintamaa, R 2001, ' Applicability of miniature size bend specimens to determine the master curve reference temperature T 0 ', Engineering Fracture Mechanics, vol. 68, no. 11, pp. 1265-1296 . https://doi.org/10.1016/S0013-7944(01)00020-0

The master curve method enables characterisation of the brittle fracture toughness based on a few relatively small specimens. Presently the general view is that pre-cracked Charpy-V specimens constitute, effectively, the smallest specimens that can b

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7794a5ef70a704562ed2eb1bc96a78e3
https://doi.org/10.1016/s0013-7944(01)00020-0

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Conservatism of ASME KIR-reference curve with respect to crack arrest

Autor: Gerhard Nagel, Kim Wallin, Rauno Rintamaa

Publikováno v: Wallin, K, Rintamaa, R & Nagel, G 2001, ' Conservatism of ASME K IR-reference curve with respect to crack arrest ', Nuclear Engineering and Design, vol. 206, no. 2-3, pp. 185-199 . https://doi.org/10.1016/S0029-5493(00)00434-9

The conservatism of the RTNDT temperature indexing parameter and the ASME KIR-reference curve with respect to crack arrest toughness, has been evaluated. Based on an analysis of the original ASME KIa data, it was established that inherently, the ASME

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::224673fea75fbe00e16c0b1016a5ff52
https://doi.org/10.1016/s0029-5493(00)00434-9

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Consistency of fracture assessment criteria for the NESC-1 thermal shock test

Autor: Kim Wallin, Rauno Rintamaa, Tapio Planman, Heikki Keinänen, Heli Talja

Publikováno v: Rintamaa, R, Wallin, K, Keinänen, H, Planman, T & Talja, H 2001, ' Consistency of fracture assessment criteria for the NESC-1 thermal shock test ', International Journal of Pressure Vessels and Piping, vol. 78, no. 2-3, pp. 125-135 . https://doi.org/10.1016/S0308-0161(01)00027-8

In this report, a best estimate analysis of the NESC Spinning Cylinder test is performed and the consistency of the state of the art application of the different fracture parameters and assessments criteria is examined. Direct fracture toughness meas

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8eca4ff358c6fc2ba9079f7d40d55b16
https://doi.org/10.1016/s0308-0161(01)00027-8

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Evaluating the NESC-I test and the integrated approach to structural integrity assessment

Autor: B.R. Bass, J. Wintle, N. Taylor, R Hurst, D McGarry, Rauno Rintamaa

Publikováno v: Hurst, R, Taylor, N, McGarry, D, Bass, B, Rintamaa, R & Wintle, J 2001, ' Evaluating the NESC-I test and the integrated approach to structural integrity assessment ', International Journal of Pressure Vessels and Piping, vol. 78, no. 2-3, pp. 213-224 . https://doi.org/10.1016/S0308-0161(01)00035-7

The NESC-I spinning cylinder test was designed to simulate selected conditions associated with an ageing reactor pressure vessel (RPV) subjected to severe pressurised thermal shock (PTS) loading and containing hypothetical flaws. It formed the focal

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bfe86947d7f368f1f203835f79959c3d
https://doi.org/10.1016/s0308-0161(01)00035-7

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The feasibility of small size specimens for testing of environmentally assisted cracking of irradiated materials and of materials under irradiation in reactor core

Autor: Aki Toivonen, Pekka Moilanen, Mika Pyykkönen, S. Tähtinen, Rauno Rintamaa

Publikováno v: Toivonen, A, Moilanen, P, Pyykkönen, M, Tähtinen, S & Rintamaa, R 1999, ' The feasibility of small size specimens for testing of environmentally assisted cracking of irradiated materials and of materials under irradiation in reactor core ', Nuclear Engineering and Design, vol. 193, no. 3, pp. 309-316 . https://doi.org/10.1016/S0029-5493(99)00186-7

Environmentally assisted cracking (EAC) or, in other words, stress corrosion cracking (SCC) of in-core materials has become an increasingly important reason for the downtime and maintenance costs of nuclear power plants (NPPs). Use of small size spec

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::68a1f05d62e81c65730b17b116b4fbf1
https://doi.org/10.1016/s0029-5493(99)00186-7

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Descriptive characteristics of different types of test for irradiation embrittlement

Autor: Kari Törrönen, Kim Wallin, Ralf Ahlstrand, Matti Valo, Rauno Rintamaa

Publikováno v: Wallin, K, Valo, M, Rintamaa, R, Törrönen, K & Ahlstrand, R 1995, ' Descriptive characteristics of different types of test for irradiation embrittlement ', Nuclear Engineering and Design, vol. 159, no. 1, pp. 69-80 . https://doi.org/10.1016/0029-5493(95)01054-L

Within the IAEA coordinated programme on optimizing of reactor pressure vessel surveillance programmes and their analysis, phase 3, a specially tailored radiation sensitive correlation monitor material, a Japanese steel plate with code designation JR

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::153ad9158392493bb854bbced2824894
https://doi.org/10.1016/0029-5493(95)01054-l

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Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel

Autor: Pekka Nurkkala, Boris Timofeev, Heikki Keinänen, Alexander Blumin, Heli Talja, Kari Törrönen, Ralf Ahlstrand, Rauno Rintamaa, George Karzov

Publikováno v: Keinänen, H, Talja, H, Rintamaa, R, Törrönen, K, Ahlstrand, R, Nurkkala, P, Karzov, G, Timofeev, B & Blumin, A 1995, ' Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel ', Nuclear Engineering and Design, vol. 158, no. 2-3, pp. 217-226 . https://doi.org/10.1016/0029-5493(95)01030-L

A joint pressure vessel integrity research programme involving three partners is being carried out during 1990–1995. The partners are the Central Research Institute of Structural Materials “Prometey” from Russia, IVO International Ltd (IVO) fro

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https://doi.org/10.1016/0029-5493(95)01030-l

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Lifetime prediction techniques for nuclear power plant systems

Autor: Heikki Keinänen, Otso Cronvall, Arja Saarenheimo, Rauno Rintamaa, Irina Aho-Mantila, Erkki Vesikari, Ulla Ehrnstén, Kaisa Simola

Publikováno v: Aho-Mantila, I, Cronvall, O, Ehrnstén, U, Keinänen, H, Rintamaa, R, Saarenheimo, A, Simola, K & Vesikari, E 2012, Lifetime prediction techniques for nuclear power plant systems . in D Féron (ed.), Nuclear Corrosion Science and Engineering . Woodhead Publishing, Cambridge, Woodhead publishing series in energy, vol. 22, pp. 449-470 . https://doi.org/10.1533/9780857095343.4.449

Advanced lifetime prediction methodologies are necessary in securing the safe and reliable operation of nuclear power plants. Stress corrosion cracking is the most common corrosion mechanism, which can cause a major integrity loss in metallic compone

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::29e1471161a7189f279e68bdb2e3c686
https://doi.org/10.1533/9780857095343.4.449

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Overview of the nuclear power plant structural integrity research in Finland

Autor: Rauno Rintamaa, Kari Mäkelä, Kim Wallin, Kari Törrönen, Päivi Karjalainen-Roikonen, Pentti Kauppinen, Heli Talja, Heikki Keinänen, Hannu Hänninen, Matti Valo, Pertti Aaltonen

Publikováno v: Törrönen, K, Aaltonen, P, Hänninen, H, Mäkelä, K, Karjalainen-Roikonen, P, Keinänen, H, Kauppinen, P, Rintamaa, R, Talja, H, Valo, M & Wallin, K 1993, ' Overview of the nuclear power plant structural integrity research in Finland ', International Journal of Pressure Vessels and Piping, vol. 55, no. 1, pp. 3-59 . https://doi.org/10.1016/0308-0161(93)90046-V

An overview of the Finnish programmes concerning safety related research in pressure boundary components of nuclear power plants is presented. The focus is on recent results in the areas of fracture mechanics, large scale component tests, irradiation

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https://doi.org/10.1016/0308-0161(93)90046-v

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Application of the advanced instrumented impact testing facility for the irradiation damage assessment

Autor: Rauno Rintamaa, Markku Nevalainen, Matti Valo

Publikováno v: Rintamaa, R, Nevalainen, M & Valo, M 1993, ' Application of the advanced instrumented impact testing facility for the irradiation damage assessment ', International Journal of Pressure Vessels and Piping, vol. 55, no. 1, pp. 89-106 . https://doi.org/10.1016/0308-0161(93)90049-Y

A new test method suitable for the dynamic fracture toughness evaluation of irradiated specimens has been developed. The method is based on the application of the new pendulum type impact tester equipped with a self-adjusting IR-laser extensometer an

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https://doi.org/10.1016/0308-0161(93)90049-y

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