
Publikationen von J. Brinkmann
Alle Typen
Zeitschriftenartikel (6)
1.
Zeitschriftenartikel
124, S. 183 - 186 (2017)
Development and analyses of self-passivating tungsten alloys for DEMO accidental conditions. Fusion Engineering and Design 2.
Zeitschriftenartikel
109-111, Pt. A, S. 1046 - 1052 (2016)
Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants. Fusion Engineering and Design 3.
Zeitschriftenartikel
9, S. 394 - 398 (2016)
Development of yttrium-containing self-passivating tungsten alloys for future fusion power plants. Nuclear Materials and Energy 4.
Zeitschriftenartikel
432 (1-3), S. 482 - 500 (2013)
Recent progress in research on tungsten materials for nuclear fusion applications in Europe. Journal of Nuclear Materials 5.
Zeitschriftenartikel
442 (1-3), S. S173 - S180 (2013)
A brief summary of the progress on the EFDA tungsten materials program. Journal of Nuclear Materials 6.
Zeitschriftenartikel
2011 (T145), 014019 (5pp) (2011)
Oxidation behaviour of silicon-free tungsten alloys for use as first wall material. Physica Scripta Konferenzbeitrag (1)
7.
Konferenzbeitrag
89 (7-8), S. 1611 - 1616 (2014)
Oxidation behaviour of bulk W-Cr-Ti alloys prepared by mechanical alloying and HIPing. 11th International Symposium on Fusion Nuclear Technology (ISFNT), Barcelona, 16. September 2013 - 20. September 2013. Fusion Engineering and Design Vortrag (6)
8.
Vortrag
Development and analyses of self-passivating tungsten alloys for DEMO operational and accidental conditions. 29th Symposium on Fusion Technology (SOFT 2016)
, Prague (2016)
9.
Vortrag
Advanced Tungsten Materials for Plasma-facing Components of DEMO and Fusion Power Plants. 12th International Symposium on Fusion Nuclear Technology (ISFNT-12), Jeju Island, Korea (2015)
10.
Vortrag
Development of Smart Self-Passivating Tungsten Alloys as Passive Safety Measure for Future Fusion Reactors. DPG-Frühjahrstagung 2015 der Fachverbände Kurzzeitphysik und Plasmaphysik, Bochum (eingereicht)
11.
Vortrag
Advanced First Wall and Heat Sink Materials. 1st IAEA DEMO Programme Workshop, Los Angeles, CA (2012)
12.
Vortrag
Tungsten materials for a fusion reactor first wall: self-passivation and high H/He particle flux effects. Challenges to Developing W-based Materials for Fusion Applications, Santa Barbara, CA (2012)
13.
Vortrag
Tiefenaufgelöste chemische Analyse von Mehrkomponenten-Oberflächenreaktionen. DGM FA Strahllinien, BAM Berlin (2011)
Poster (9)
14.
Poster
Investigations on the technical production of selfpassivating tungsten alloys. 17th International Conference on Fusion Reactor Materials (ICFRM-17), Aachen (eingereicht)
15.
Poster
Safety improvement of a future nuclear fusion power plant by self-passivating tungsten alloys. The Nuclear Materials Conference (NuMat 2014), Clearwater, FL (eingereicht)
16.
Poster
Oxidation behavior and plasma-wall interaction of tungsten alloys for use as plasma facing material in future fusion devices. HEPP Colloquium 2013, Strausberg (2013)
17.
Poster
Manufacturing and oxidation behaviour of bulk self-passivating tungsten-based alloys. 11th International Symposium on Fusion Nuclear Technology (ISFNT-11), Barcelona (2013)
18.
Poster
Depth-resolved Deuterium Concentration of Plasma-exposed Tungsten Alloys. 19th International Workshop on Inelastic Ion-Surface Collisions (IISC-19), Frauenchiemsee (2012)
19.
Poster
Self-passivating tungsten alloys - Oxidation behaviour of thin films and bulk material. 15th International Conference of Fusion Reactor Materials (ICFRM-15), Charleston, SC (2011)
20.
Poster
A brief summary of the progress on the EFDA tungsten materials programme. 15th International Conference on Fusion Reactor Materials (ICFRM-15), Charleston, SC (2011)