Publikationen von F. Warmer
Alle Typen
Zeitschriftenartikel (40)
2019
Zeitschriftenartikel
146, Pt. B, S. 1820 - 1823 (2019)
Analysis of technical and economic parameters of fusion power plants in future power systems. Fusion Engineering and Design
Zeitschriftenartikel
61, 014016 (2019)
Gyrokinetic microinstability analysis of high-Ti and high-Te isotope plasmas in Large Helical Device. Plasma Physics and Controlled Fusion
Zeitschriftenartikel
59, 126040 (2019)
Isotope effects on energy, particle transport and turbulence in electron cyclotron resonant heating plasma of the Large Helical Device. Nuclear Fusion
Zeitschriftenartikel
146, Pt. B, S. 2259 - 2263 (2019)
First considerations on the Balance of Plant for a HELIAS fusion power plant. Fusion Engineering and Design 2018
Zeitschriftenartikel
136, Pt. A, S. 345 - 349 (2018)
Neutronics analyses for a stellarator power reactor based on the HELIAS concept. Fusion Engineering and Design
Zeitschriftenartikel
58, 106028 (2018)
Realization of high Ti plasmas and confinement characteristics of ITB plasmas in the LHD deuterium experiments. Nuclear Fusion
Zeitschriftenartikel
58, 106025 (2018)
Energy confinement of hydrogen and deuterium electron-root plasmas in the Large Helical Device. Nuclear Fusion
Zeitschriftenartikel
58, 016017 (2018)
First steps towards modeling of ion-driven turbulence in Wendelstein 7-X. Nuclear Fusion
Zeitschriftenartikel
13, 1402124 (2018)
Effect of Electron Cyclotron Current Drive on the Ion Temperature in the Plasma Core Region of the Large Helical Device. Plasma and Fusion Research 2017
Zeitschriftenartikel
57, 066016 (2017)
The effect of transient density profile shaping on transport in large stellarators and heliotrons. Nuclear Fusion
Zeitschriftenartikel
124, S. 1207 - 1210 (2017)
Verification of different Monte Carlo approaches for the neutronic analysis of a stellarator. Fusion Engineering and Design
Zeitschriftenartikel
123, S. 47 - 53 (2017)
From W7-X to a HELIAS fusion power plant: On engineering considerations for next-step stellarator devices. Fusion Engineering and Design
Zeitschriftenartikel
57, 102020 (2017)
Major results from the first plasma campaign of the Wendelstein 7-X stellarator. Nuclear Fusion
Zeitschriftenartikel
57, 126016 (2017)
Extended capability of the integrated transport analysis suite, TASK3D-a, for LHD experiment. Nuclear Fusion 2016
Zeitschriftenartikel
58, 074006 (2016)
From W7-X to a HELIAS fusion power plant: motivation and options for an intermediate-step burning-plasma stellarator. Plasma Physics and Controlled Fusion
Zeitschriftenartikel
44 (9, Part 1), S. 1576 - 1585 (2016)
System Code Analysis of HELIAS-Type Fusion Reactor and Economic Comparison with Tokamaks. IEEE Transactions on Plasma Science
Zeitschriftenartikel
44 (9, Part 1), S. 1466 - 1471 (2016)
Wendelstein 7-X Program – Demonstration of a Stellarator Option for Fusion Energy. IEEE Transactions on Plasma Science 2015
Zeitschriftenartikel
91, S. 60 - 66 (2015)
HELIAS module development for systems codes. Fusion Engineering and Design
Zeitschriftenartikel
98-99, S. 2227 - 2230 (2015)
Implementation and verification of a HELIAS module for the systems code PROCESS. Fusion Engineering and Design
Zeitschriftenartikel
68 (4), S. 727 - 740 (2015)
Limits of Confinement Enhancement for Stellarators. Fusion Science and Technology