Zobrazeno 1 - 10
of 73
pro vyhledávání: '"W. van Witzenburg"'
Publikováno v:
Journal of Nuclear Materials. :92-99
Advantages of vanadium alloys for fusion reactor structural applications are: low induced activation, excellent thermal stress factor, high strength at elevated temperatures, and superior ductility at low temperatures. Resistance to irradiation damag
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 (
Publikováno v:
Journal of Nuclear Materials. :460-465
The effect of oxygen injection on the mechanical properties of vanadium alloys was investigated. Tensile testing of oxygen-containing and reference specimens were performed at temperatures up to 1000°C. Results show that, in general, oxygen decrease
Publikováno v:
Journal of Nuclear Materials. 227:304-311
Helium preimplantation and neutron irradiation influence on the tensile properties of vanadium alloys in the irradiation/test temperature range of 500–800°C were investigated and principal physical mechanisms of the mechanical behaviour of the irr
Publikováno v:
Fusion Engineering and Design. 29:399-410
Vanadium alloys have been identified as a leading candidate material for fusion first-wall—blanket applications. Certain vanadium alloys exhibit favorable safety and environmental characteristics, good fabricability, high temperature and heat load
The effect of preimplanted helium on the microstructure of neutron irradiated pure niobium and two dilute niobium alloys, Nb-1%Zr and Nb-1%Zr-0.4%Mo, was investigated by electron microscopy. Helium was implanted in the materials by means of a cyclotr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::11c2907c257988e4237a1f4c26ba2284
https://doi.org/10.1520/stp34349s
https://doi.org/10.1520/stp34349s
A large number of Al 5154-0 tensile test specimens were irradiated in a core position facility of the High Flux Reactor in Petten, the Netherlands. They were withdrawn from the irradiation rig in seven batches with successively higher accumulated neu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b2d7687538962fe62605f9517b5cf77
https://doi.org/10.1520/stp34378s
https://doi.org/10.1520/stp34378s
In the framework of the material research programme for the first wall of fusion reactors, the mechanical behaviour of the individual zones of irradiated AISI 316 welded joints (parent metal, heat affected zone and weld-deposited metal) has been inve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4b9260b2b7f803559a78a8a630ad8612
https://doi.org/10.1016/b978-0-444-88508-1.50053-0
https://doi.org/10.1016/b978-0-444-88508-1.50053-0
Publikováno v:
Journal of Chemical Physics; 9/28/2023, Vol. 159 Issue 12, p1-12, 12p