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
: Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants. Fusion Engineering and Design 109-111, Pt. A, S. 1046 - 1052 (2016)
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
: Recent progress in research on tungsten materials for nuclear fusion applications in Europe. Journal of Nuclear Materials 432 (1-3), S. 482 - 500 (2013)
5.
Zeitschriftenartikel
: A brief summary of the progress on the EFDA tungsten materials program. Journal of Nuclear Materials 442 (1-3), S. S173 - S180 (2013)
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)