Development of a spectrum method for modelling fatigue due to thermal mixing

Autor: Timperi, Antti

Publikováno v: In Nuclear Engineering and Design May 2018 331:136-146

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021

Autor: Blouin, Arnaud, Marie, Stephane, Nicak, Tomas, Timperi, Antti, Gill, Peter

Publikováno v: Blouin, A, Marie, S, Nicak, T, Timperi, A & Gill, P 2022, Advanced structural integrity assessment tools for safe long term operation-Atlas+ project : Status of the activities of the wp3 on modelling in 2020 & 2021 . in ASME 2022 Pressure Vessels & Piping Conference, PVP2022 . vol. 4A, PVP2022-84842, American Society of Mechanical Engineers (ASME), ASME 2022 Pressure Vessels and Piping Conference, PVP 2022, Las Vegas, United States, 17/07/22 . https://doi.org/10.1115/PVP2022-84842

The main objective and mission of the ATLAS+ project was to develop advanced structural assessment tools to address the remaining technology gaps for the safe and long term operation of nuclear reactor pressure coolant boundary systems. ATLAS+ WP3 fo

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7541354efed7f45154d15762ef6b82c6
https://doi.org/10.1115/pvp2022-84842

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation: ATLAS+ Project — Status of the Activities of the WP3 on Modelling in 2020

Autor: Blouin, Arnaud, Marie, Stéphane, Nicak, Tomas, Timperi, Antti, Gill, Peter

Publikováno v: Blouin, A, Marie, S, Nicak, T, Timperi, A & Gill, P 2020, Advanced structural integrity assessment tools for safe long term operation : Atlas+ project-Status of the activities of the WP3 on modelling in 2020 . in ASME 2020 Pressure Vessels & Piping Conference : Materials and Fabrication . vol. 6, V006T06A046, American Society of Mechanical Engineers (ASME), American Society of Mechanical Engineers. Pressure Vessels and Piping Division. Publication PVP, vol. 2020, ASME 2020 Pressure Vessels and Piping Conference, PVP 2020, Virtual, Online, 3/08/20 . https://doi.org/10.1115/PVP2020-21551

The main objective and mission of the ATLAS+ project is to develop advanced structural assessment tools to address the remaining technology gaps for the safe and long term operation of nuclear reactor pressure coolant boundary systems. ATLAS+ WP3 foc

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::772f3620237f5db06c6b0c5dc1e111df
https://doi.org/10.1115/pvp2020-21551

Numerical modelling of condensation pool (NUMPOOL)

Autor: Pättikangas, Timo, Niemi, Jarto, Timperi, Antti, Chauhan, Michael

Publikováno v: Pättikangas, T, Niemi, J, Timperi, A & Chauhan, M 2013, Numerical modelling of condensation pool (NUMPOOL) . 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. 178-185 . < https://publications.vtt.fi/pdf/technology/2013/T80.pdf#page=180 >

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::1a58a99016baee6c2638593cf66d9ba7
https://cris.vtt.fi/en/publications/8db4356f-b75a-4e9c-a405-b1a5f1084cbd

Fracture Assessment of Reactor Circuit (FRAS):FRAS summary report

Autor: Karjalainen-Roikonen, Päivi, Calonius, Kim, Timperi, Antti, Cronvall, Otso, Keinänen, Heikki, Kuutti, Juha, Kaunisto, Kalle, Laukkanen, Anssi, Elers, Lauri, Valo, Matti, Lappalainen, Petteri, Planman, Tapio, Nevasmaa, Pekka

Publikováno v: Karjalainen-Roikonen, P, Calonius, K, Timperi, A, Cronvall, O, Keinänen, H, Kuutti, J, Kaunisto, K, Laukkanen, A, Elers, L, Valo, M, Lappalainen, P, Planman, T & Nevasmaa, P 2011, Fracture Assessment of Reactor Circuit (FRAS) : FRAS 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. 414-429 . < https://publications.vtt.fi/pdf/tiedotteet/2011/T2571.pdf >

The FRAS project (Fracture assessment of reactor circuit) project aims at (i) calculation of design and unforeseeable loads and their effects on a structure by applying numerical modelling; (ii) development of advanced fracture mechanics assessment t

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=355e65625b88::8e6398e7cc32c27f80d0f9d65e876131
https://cris.vtt.fi/en/publications/9cc2e656-597a-49b3-92b1-3bd19f6aaf24