Publications of G. Orozco
All genres
Journal Article (20)
2023
Journal Article
189, 113471 (2023)
3D magnetic field measurements and improvements at the negative ion source BATMAN Upgrade. Fusion Engineering and Design 2022
Journal Article
2244, 012049 (2022)
Ion source developments at IPP: On the road towards achieving the ITER-NBI targets and preparing concepts for DEMO. Journal of Physics: Conference Series
Journal Article
2244, 012053 (2022)
ITER-HNB plasma and extraction grids in BUG: Characterization of magnetic deflection correction. Journal of Physics: Conference Series
Journal Article
2244, 012051 (2022)
Overview of recent and upcoming activities at the BATMAN Upgrade test facility. Journal of Physics: Conference Series 2021
Journal Article
173, 112837 (2021)
Computational design of magnetic beamlet deflection correction for NNBI. Fusion Engineering and Design
Journal Article
2373 (1), 030004 (2021)
Impact of operational parameters on single beamlet deflection in a negative ion source for NBI applications. AIP Conference Proceedings
Journal Article
11, 025330 (2021)
First direct comparison of whole beam and single beamlet divergences in a negative ion source with simultaneous BES and CFC tile calorimetry measurements editors-pick. AIP Advances
Journal Article
165, 112225 (2021)
Design and first results of a retractable 1D-CFC beam target for BATMAN upgrade. Fusion Engineering and Design 2020
Journal Article
62, 025023 (2020)
Analytical Beamlet Code 3D for neutral beam injectors: principles and applications. Plasma Physics and Controlled Fusion
Journal Article
91, 013511 (2020)
Simulation of the gas density distribution in the accelerator of the ELISE test facility. Review of Scientific Instruments
Journal Article
91, 013509 (2020)
Beamlet scraping and its influence on the beam divergence at the BATMAN Upgrade test facility. Review of Scientific Instruments 2019
Journal Article
146, Pt. A, pp. 518 - 521 (2019)
Modeling neutral beam transport in fusion experiments: Studying the effects of reionisation and deflection. Fusion Engineering and Design
Journal Article
59, 112004 (2019)
Overview of first Wendelstein 7-X high-performance operation. Nuclear Fusion
Journal Article
146, Pt. B, pp. 2105 - 2109 (2019)
Reviewed design of the high heat flux panels for the AUG and W7-X neutral beam calorimeter. Fusion Engineering and Design
Journal Article
26, 082504 (2019)
Performance of Wendelstein 7-X stellarator plasmas during the first divertor operation phase. Physics of Plasmas 2017
Journal Article
123, pp. 381 - 384 (2017)
Characterization and performance improvement of the large titanium sublimation pumps in the AUG and W7‐X neutral beam injectors. Fusion Engineering and Design
Journal Article
57, 102020 (2017)
Major results from the first plasma campaign of the Wendelstein 7-X stellarator. Nuclear Fusion 2016
Journal Article
44 (9, Part 1), pp. 1553 - 1558 (2016)
Optimization of Large Titanium Sublimation Pumps for the Neutral Beam Injection System on AUG and W7-X. IEEE Transactions on Plasma Science 2015
Journal Article
100, pp. 453 - 460 (2015)
Design of the torus interface for the neutral beam injectors of Wendelstein 7-X. Fusion Engineering and Design 2013
Journal Article
88 (9-10), pp. 1764 - 1767 (2013)
Hydraulic analysis of the Wendelstein 7-X cooling loops. Fusion Engineering and Design