Zobrazeno 1 - 10
of 35
pro vyhledávání: '"Hans-Werner Viehrig"'
Publikováno v:
Crystals, Vol 8, Iss 8, p 306 (2018)
Secondary cracks are known to absorb energy, retard primary crack propagation and initiate at lower loads than primary cracks. They are observed more often in hot-rolled than in hot-extruded ODS steels. In this work, the microstructural factors respo
Externí odkaz:
https://doaj.org/article/0f74a48c7431478a93272bdf41fbd8d7
Publikováno v:
International Review of Nuclear Reactor Pressure Vessel Surveillance Programs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b4805151ca98e427c9e2812d3abae373
https://doi.org/10.1520/stp160320160127
https://doi.org/10.1520/stp160320160127
Publikováno v:
International Journal of Pressure Vessels and Piping. :36-51
The multi-layer beltline welding seam of the Biblis C reactor pressure vessel was characterized by hardness, tensile, ISO-V impact and fracture toughness testing. The reference temperature, T0, was determined according to the test standard ASTM E1921
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::badb0f94aef1d64759ad0b452c79cc26
https://doi.org/10.1016/j.ijpvp.2015.10.002
https://doi.org/10.1016/j.ijpvp.2015.10.002
Publikováno v:
Journal of Nuclear Materials 456(2015), 334-343
The focus of this paper is on the irradiation response and the effect of thermal annealing in weld materials extracted from decommissioned WWER 440 reactor pressure vessels of the nuclear power plant Greifswald. The characterisation is based on the m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::00f99db214f52aaec741d37690d49335
https://doi.org/10.1016/j.jnucmat.2014.10.004
https://doi.org/10.1016/j.jnucmat.2014.10.004
Publikováno v:
Journal of Nuclear Materials 491(2017), 83-93
ODS steels have been known to exhibit anisotropic fracture behaviour and form secondary cracks. In this work, the factors responsible for the anisotropic fracture behaviour have been investigated using scanning electron microscopy and electron backsc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8eba055bfbea66f162f01f36bdc104a8
https://www.hzdr.de/publications/Publ-25455-1
https://www.hzdr.de/publications/Publ-25455-1
Publikováno v:
Engineering Fracture Mechanics. 129:26-37
The fracture behaviour of a component or specimen that contains a sharp notch is governed essentially by the same theoretical relations known from cracks. The blunt notch root only causes an increase of the resistance against crack initiation, which
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0691c2665eeab15cb27becea14efc8f9
https://doi.org/10.1016/j.engfracmech.2014.07.022
https://doi.org/10.1016/j.engfracmech.2014.07.022
Autor:
A. Ballesteros, K. Wilford, Marta Serrano, Hieronymus Hein, Elisabeth Keim, Rachid Chaouadi, Frank Bergner, Hans-Werner Viehrig, Eberhard Altstadt
Publikováno v:
Nuclear Engineering and Design 278(2014), 753-757
LONGLIFE (“Treatment of long term irradiation embrittlement effects in RPV safety assessment”) was a collaborative project of the 7th Framework Programme of EURATOM under the umbrella of NULIFE/NUGENIA, aiming at an improved understanding of irra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d4ceced406e0c128e7c7d8bcf43dae23
https://doi.org/10.1016/j.nucengdes.2014.09.003
https://doi.org/10.1016/j.nucengdes.2014.09.003
Publikováno v:
Viehrig, H-W, Altstadt, E, Houska, M & Valo, M 2012, ' Fracture mechanics characterisation of the beltline welding seam of the decommissioned WWER-440 reactor pressure vessel of nuclear power plant Greifswald Unit 4 ', International Journal of Pressure Vessels and Piping, vol. 89, pp. 129-136 . https://doi.org/10.1016/j.ijpvp.2011.10.016
International Journal of Pressure Vessels and Piping 89(2012), 129-136
International Journal of Pressure Vessels and Piping 89(2012), 129-136
The paper presents data measured for trepans sampled from the decommissioned WWER-440 reactor pressure vessel of the NPP Greifswald Unit 4. The main focus of this work is on fracture toughness characterisation according to test standard ASTM E1921. L
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::dd0311e2b33a062de6a9db906b72351b
https://doi.org/10.1016/j.ijpvp.2011.10.016
https://doi.org/10.1016/j.ijpvp.2011.10.016
Publikováno v:
Journal of Nuclear Materials. 499:652
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::14566ba4e2a61d9bfdf3e4a6121a274b
https://doi.org/10.1016/j.jnucmat.2017.11.032
https://doi.org/10.1016/j.jnucmat.2017.11.032
Autor:
Hans-Werner Viehrig, Jörg Konheiser, Birgit Gleisberg, Udo Rindelhardt, Jan Schuhknecht, Klaus Noack
Publikováno v:
Nuclear Engineering and Design 239(2009)9, 1581-1590
The real toughness response of RPV material can only be determined after the final shut down of the NPP. Such a chance is given now by investigating material from the former Greifswald NPP (VVER-440/230). In the first part the paper deals with fast n
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ccda934ab0bc50f668da4c559bd3550c
https://doi.org/10.1016/j.nucengdes.2008.07.018
https://doi.org/10.1016/j.nucengdes.2008.07.018