Zobrazeno 1 - 10
of 14
pro vyhledávání: '"Pekka Moilanen"'
Publikováno v:
Metals, Vol 14, Iss 2, p 154 (2024)
A miniature pneumatic bellows device was designed for in-situ testing inside the scanning electron microscope. The device uses a pneumatic actuator to load the specimen and displacement is directly monitored with a linear variable differential transf
Externí odkaz:
https://doaj.org/article/676365dbf89f4aee9356914b65e9d703
Autor:
Caitlin Huotilainen (Hurley), Ville Tulkki, Pekka Moilanen, Petri Kinnunen, Alejandro Revuelta, Gilles Bignan
Publikováno v:
Huotilainen, C, Tulkki, V, Moilanen, P, Kinnunen, P, Revuelta, A & Bignan, G 2019, Jules Horowitz Reactor-the Future of European Materials Testing Reactors . in SYP2019 Proceedings : Nuclear Science and Technology Symposium-SYP2019 . Finnish Nuclear Society, Nuclear Science and Technology Symposium, NST 2019, Helsinki, Finland, 20/10/19 . < https://ats-fns.fi/images/files/2019/syp2019/presentations/TSFM2_CHuotilainen_JulesHorowitzReactor%E2%80%93TheFutureOfEuropeanMaterialsTestingReactors_Tier1paper.pdf >
VTT Technical Research Centre of Finland-PURE
VTT Technical Research Centre of Finland-PURE
As the mean age of the existing fleet of currently operating European materials testing reactors approaches fifty years, the need for a new facility, to ensure continuity and provide the necessary support to the nuclear power plant community and nucl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::0da27a9bbea1d4f19b9a543ef39f4a5d
https://cris.vtt.fi/en/publications/fde90bc6-6b51-4d24-9082-7f6b2aa67765
https://cris.vtt.fi/en/publications/fde90bc6-6b51-4d24-9082-7f6b2aa67765
Publikováno v:
Penttilä, S, Moilanen, P, Karlsen, W & Toivonen, A 2018, ' Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions : Case Supercritical Water ', Journal of Nuclear Engineering and Radiation Science, vol. 4, no. 1, 021006 . https://doi.org/10.1115/1.4037897
The presented work consists of a test setup study of a new pneumatic material testing device based on double bellows (DBs) loading device and with miniature autoclaves enabling applications at temperature and pressure up to 650 °C and 35 MPa, respec
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::06d307e1a509b0a2fe6339c65985de1a
https://doi.org/10.1115/1.4037897
https://doi.org/10.1115/1.4037897
Publikováno v:
Pohja, R, Nurmela, A, Moilanen, P & Holmström, S 2013, ' Multifunctional high precision pneumatic loading system (HIPS) for creep-fatigue testing ', Procedia Engineering, vol. 55, pp. 573-577 . https://doi.org/10.1016/j.proeng.2013.03.297
The first successful application of the high precision pneumatic loading system for advanced material testing was developed at VTT in 1995. The pneumatic servo-controlled loading system is capable of operating in a range of extreme conditions such as
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2b68bda5e9d0eccb883c52d665357dff
https://doi.org/10.1016/j.proeng.2013.03.297
https://doi.org/10.1016/j.proeng.2013.03.297
Publikováno v:
Holmström, S, Pohja, R, Nurmela, A, Moilanen, P & Auerkari, P 2013, ' Creep and creep-fatigue behaviour of 316 stainless steel ', Procedia Engineering, vol. 55, pp. 160-164 . https://doi.org/10.1016/j.proeng.2013.03.236
The austenitic stainless steel 316 is of current interest as structural material for the future Gen IV nuclear power plants operating at high temperatures. Although 316 steel grades have been studied for the service conditions of current nuclear and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::047243b8da8a09f0b60eef139832746e
https://doi.org/10.1016/j.proeng.2013.03.236
https://doi.org/10.1016/j.proeng.2013.03.236
Autor:
Ville Tulkki, Ulla Ehrnstén, Pekka Moilanen, Juhani Rantala, Rami Pohja, Stefan Holmström, Santtu Huotilainen
Publikováno v:
Pohja, R, Moilanen, P, Rantala, J, Huotilainen, S, Tulkki, V, Ehrnstén, U & Holmström, S 2016, ' Multiaxial creep testing device for nuclear fuel claddings ', Athens Journal of Sciences, vol. 3, no. 3, pp. 227-240 . < http://www.athensjournals.gr/ajs/past/v3i3 >
VTT Technical Research Centre of Finland-PURE
VTT Technical Research Centre of Finland-PURE
Mechanical properties and creep resistance are among the key issues in the selection of fuel cladding materials for future Gen-IV nuclear reactor applications. As for today's nuclear reactors, the Fukushima accident has increased the interest in acci
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d8064fae09d3afd6fd151057445db72e
https://cris.vtt.fi/en/publications/63c37e65-ed13-4090-90b9-5a12a68d79ef
https://cris.vtt.fi/en/publications/63c37e65-ed13-4090-90b9-5a12a68d79ef
Autor:
Rami Pohja, Ville Tulkki, Timo Ikonen, Pekka Moilanen, Juhani Rantala, Santtu Huotilainen, Ulla Ehrnstén
Publikováno v:
Pohja, R, Tulkki, V, Ikonen, T, Moilanen, P, Rantala, J, Huotilainen, S & Ehrnstén, U 2016, Creep performance of fuel cladding . in P Auerkari (ed.), Baltica X : International Conference on Life Management and Maintenance for Power Plants . VTT Technical Research Centre of Finland, Espoo, VTT Technology, vol. 261, BALTICA X-International Conference on Life Management and Maintenance for Power Plants, Helsinki-Stockholm, Finland, 7/06/16 . < https://publications.vtt.fi/pdf/technology/2016/T261.pdf >
VTT Technical Research Centre of Finland-PURE
VTT Technical Research Centre of Finland-PURE
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and reliably the thermal performance and mechanical integrity of fuel rods. Fuel cladding tubes experience a range of changing conditions during their re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::c9ffb70316fda0e238e5c993614865e4
https://cris.vtt.fi/en/publications/e11a8b21-df39-4101-aa1f-2923dca3b36b
https://cris.vtt.fi/en/publications/e11a8b21-df39-4101-aa1f-2923dca3b36b
Publikováno v:
Tähtinen, S, Moilanen, P & Singh, B N 2007, ' Effect of displacement dose and irradiation temperature on tensile and fracture toughness properties of titanium alloys ', Journal of Nuclear Materials, vol. 367-370, no. Part A, pp. 627-632 . https://doi.org/10.1016/j.jnucmat.2007.03.042
At a low dose level of 0.001 dpa the Ti6Al4V (α + β) alloy showed softening and at higher doses an increase in hardening and lack of work hardening after irradiation at 60 °C. The (α + β) alloy seemed to suffer from plastic instability when irra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c81d9ceb467118eaf8019174daacc871
https://doi.org/10.1016/j.jnucmat.2007.03.042
https://doi.org/10.1016/j.jnucmat.2007.03.042
Publikováno v:
Singh, B N, Tähtinen, S, Moilanen, P, Jacquet, P & Dekeyser, J 2003, ' In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC ', Journal of Nuclear Materials, vol. 320, no. 3, pp. 299-304 . https://doi.org/10.1016/S0022-3115(03)00234-4
Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::94d075fcf27de2430571d7c346f190db
https://doi.org/10.1016/S0022-3115(03)00234-4
https://doi.org/10.1016/S0022-3115(03)00234-4
Publikováno v:
Tähtinen, S, Moilanen, P, Singh, B N & Edwards, D J 2002, ' Tensile and fracture toughness properties of unirradiated and neutron irradiated titanium alloys ', Journal of Nuclear Materials, vol. 307-311, no. Part 1, pp. 416-420 . https://doi.org/10.1016/S0022-3115(02)01010-3
In the unirradiated condition the Ti6Al4V (α+β) alloy has slightly higher tensile strength and noticeably lower ductility compared to that of the Ti5Al2.5Sn (α) alloy both at 50 and 350 °C. The fracture toughness behaviour of both alloys is simil
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e76fedbbf7389e639a665050f8eacff8
https://cris.vtt.fi/en/publications/d51cbe9f-8584-4721-b2b3-425cc82136e9
https://cris.vtt.fi/en/publications/d51cbe9f-8584-4721-b2b3-425cc82136e9