Zobrazeno 1 - 10
of 21
pro vyhledávání: '"E.V. van Osch"'
Publikováno v:
Fusion Engineering and Design. :775-779
In the frame of the ITER task BL 14.1, the residual strength of precipitation hardened Inconel 718 bolts, preloaded to stresses up to 90% of the yield strength, after neutron irradiation has been investigated. In the ITER design, the Inconel 718 bolt
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8bdde91e6485ba5c9eadf9fbfda7d35e
https://doi.org/10.1016/s0920-3796(01)00567-1
https://doi.org/10.1016/s0920-3796(01)00567-1
Publikováno v:
Journal of Nuclear Materials. :1201-1205
The irradiation behaviour of electron beam (EB) and tungsten inert gas (TIG) welded joints of the reduced-activation martensitic steel IEA heat F82H-mod. was investigated by neutron irradiation experiments in the high flux reactor (HFR) in Petten. Me
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::857c158dc5d469fe5bbfe40aad8cab42
https://doi.org/10.1016/s0022-3115(00)00152-5
https://doi.org/10.1016/s0022-3115(00)00152-5
Autor:
E.V. van Osch, M.I. de Vries
Publikováno v:
Journal of Nuclear Materials. :162-166
In the framework of the European Long Term Fusion Technology Program, Advanced Materials Field, ECN has been working on the assessment of low temperature irradiation hardening and embrittlement of vanadium alloys, as being developed for fusion applic
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e49eea20adaf6076be650d19cabbb50d
https://doi.org/10.1016/s0022-3115(98)00704-1
https://doi.org/10.1016/s0022-3115(98)00704-1
Publikováno v:
Journal of Nuclear Materials. :301-307
In the frame work of the European Fusion Technology Programme and the International Thermonuclear Experimental Reactor (ITER), ECN is investigating the irradiation behaviour of the structural materials for ITER. The main structural material for ITER
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a0fac4a3c8aa04805febf8078debc880
https://doi.org/10.1016/s0022-3115(98)00362-6
https://doi.org/10.1016/s0022-3115(98)00362-6
Autor:
H. Matsui, D.L. Smith, E.V. van Osch, Arthur F. Rowcliffe, Steven J. Zinkle, V.A. Kazakov, K. Abe
Publikováno v:
Journal of Nuclear Materials. :205-214
The current status of research and development on unirradiated and irradiated V-Cr-Ti alloys intended for fusion reactor structural applications is reviewed, with particular emphasis on the flow and fracture behavior of neutron-irradiated vanadium al
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::21317fbed434f604e6cf5ba8b233a3e0
https://doi.org/10.1016/s0022-3115(98)00269-4
https://doi.org/10.1016/s0022-3115(98)00269-4
Publikováno v:
Journal of Nuclear Materials. :1966-1972
Tokamak blankets have complex shapes and geometries with double curvature and embedded cooling channels. Usual manufacturing techniques such as forging, bending and welding generate very complex fabrication routes. Hot Isostatic Pressing (HIP) is a v
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ef754ec74c664229f578f331b15140a5
https://doi.org/10.1016/s0022-3115(98)00416-4
https://doi.org/10.1016/s0022-3115(98)00416-4
Autor:
M.I. de Vries, G.P. Tartaglia, R. Conrad, M.G. Horsten, E.V. van Osch, W. van Witzenburg, G. Sordon
Publikováno v:
Journal of Nuclear Materials. :1541-1546
Copyright (c) 1996 Elsevier Science B.V. All rights reserved. JRC, Petten Establishment, and ECN combine the full range of facilities required for the investigation of irradiation damage of fusion reactor structural materials. The high flux reactor (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bb11cb8f02a2813244f278aa3b95ab32
https://doi.org/10.1016/s0022-3115(96)00134-1
https://doi.org/10.1016/s0022-3115(96)00134-1
Autor:
J.G. van der Laan, E.V. van Osch
Publikováno v:
Journal of Nuclear Materials. :781-784
Carbon base candidate plasma facing materials have been subjected in the enhanced high power ECN-laser facility to short pulse high heat loads as anticipated to occur during plasma disruptions in next step devices like the International Thermonuclear
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b682377499de0aca2d8488a26b4501ef
https://doi.org/10.1016/0022-3115(94)00584-2
https://doi.org/10.1016/0022-3115(94)00584-2
Publikováno v:
Journal of Nuclear Materials. 211:135-140
Plasma-sprayed boron carbide coatings have been manufactured by different suppliers onto substrates of type 316L stainless steel. The coating thickness ranges from 0.3 to 2.0 mm. The larger thicknesses could only be achieved by application of an adap
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ee11ff9af38ed41590cb160bb2bfc888
https://doi.org/10.1016/0022-3115(94)90363-8
https://doi.org/10.1016/0022-3115(94)90363-8
Autor:
H. Bolt, E.V. van Osch, J.G. van der Laan, J. Linke, H. Nickel, Masato Akiba, E. Wallura, S. Suzuki
Publikováno v:
Journal of Nuclear Materials. :607-611
An important issue for the next step thermonuclear fusion devices is the development of a reliable engineering solution for the first wall and in particular for the divertor. Besides severe mechanical loads, these plasma facing components (PFC) will
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b65b196e119305bdce46cd4960fb6e4
https://doi.org/10.1016/s0022-3115(06)80108-x
https://doi.org/10.1016/s0022-3115(06)80108-x