Publications of W. Daenner
All genres
Talk (5)
101.
Talk
Critical Design Issues of Wendelstein 7-X. 15th International Stellarator Workshop, Madrid (2005)
102.
Talk
Design and test of the support elements of the W7-X magnet system. 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE), Knoxville,TN (2005)
103.
Talk
Moegliche Typen des Fusionsreaktors, reaktorphysikalische und reaktortechnische Probleme bei seiner Entwicklung. Reaktortagung, Bonn (1971)
Poster (2)
104.
Poster
Stability test of a superconducting Wendelstein 7-X coil with respect to mechanical disturbances. 21st International Conference on Magnet Technology (MT-21), Hefei, Anhui (2009)
105.
Poster
Evaluation of the structural mechanical behaviour of W7-X central support connections by means of semi-automated FE analysis. 25th Symposium on Fusion Technology (SOFT 2008), Rostock (2008)
Report (16)
106.
Report
Estimates for Helium Cooling of a Modular DEMO First Wall. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1982), 52 pp.
107.
Report
MHD-Druckverluste in Rohrleitungssystemen für toroidale Fusionsreaktoren. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1979), 75 pp.
108.
Report
The Mechanical Performance of the Fusion Reactor First Wall. Part II: Behaviour under pulsed load conditions. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1977), 104 pp.
109.
Report
AKTIV. - A computer program for evaluating the activity, afterheat, and biological hazard potential for stainless steel structures in fusion reactor blankets. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1977), 42 pp.
110.
Report
Energie durch Kernfusion. Physikalische Grundlagen, Energiereserven, Stand der Plasmaphysik, Reaktorentwürfe, Schlüsselprobleme, Kostenaspekte, Sicherheit und Umweltbeeinträchtigungen. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1976), 179 pp.
111.
Report
The Mechanical Performance of the Fusion Reactor First Wall. Part I: Steady-state analysis without irradiation effects. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1976), 82 pp.
112.
Report
INDRA: A Program System for Calculating the Neutronics and Photonics Characteristics of a Fusion Reactor Blanket. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1976), 167 pp.
113.
Report
A preliminary model for estimating the first wall lifetime of a fusion reactor. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1975), getr. pag. pp.
114.
Report
The MHD pressure losses as a possible criterion for the selection of structure materials for fusion reactor blankets. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1974), 14 pp.
115.
Report
SYSTEMS. A computer program for evaluating the main physical and technological parameters of fusion reactors. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1974), getr. pag. pp.
116.
Report
Tritium Economy and Tritium Safety of Fusion Power Plants. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1974), 58 pp.
117.
Report
Lithium und Flibe als Kühlmittel für Fusionsreaktor-Blankets. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1972), 20 pp.
118.
Report
Neutron Flux Asymmetric in Toroidal Geometries. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1972), 43 pp.
119.
Report
Technologische Entwicklungen zum Fusionsreaktor. - Technological Developments towards a Fusion Reactor. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1972), 17 pp.
120.
Report
Mögliche Typen des Fusionsreaktors, reaktorphysikalische und -technische Probleme bei seiner Entwicklung. Max-Planck-Institut für Plasmaphysik, Garching (DE) (1971), 14 pp.