61 results on '"Heitzenroeder, P."'
Search Results
2. Progress on NSTX center stack upgrade
3. Reduction of Ekman circulation within Taylor-Couette flow
4. Recent advances in design and R&D for the Quasi-Poloidal Stellarator experiment
5. ARIES-AT magnet systems
6. The ARIES-AT advanced tokamak, Advanced technology fusion power plant
7. Modular coil design developments for the National Compact Stellarator Experiment (NCSX)
8. Heavy ion fusion (HIF) driver point designs
9. The design of the Tokamak Physics Experiment (TPX)
10. Next step spherical torus design studies
11. Design of the quasi-poloidal stellarator experiment (QPS)
12. Engineering design of the National Spherical Torus Experiment
13. Identifying the cause of the NSTX TF coil bundle failure.
14. Design analysis and manufacturing studies for ITER In-Vessel Coils.
15. Facilities for quasi-axisymmetric stellarator research.
16. A small rectangular Edge Localized Mode control coil design able to withstand a 400°C environment.
17. Iter In-Vessel Coil design and R&D.
18. Accomplishments in Field Period Assembly for NCSX This is how we did it.
19. Engineering cost & schedule lessons learned on NCSX.
20. Testing of compact bolted fasteners with insulation and friction-enhanced shims for NCSX.
21. National spherical torus experiment (NSTX) Center Stack Upgrade.
22. Progress in NCSX Construction.
23. NCSX Component Fabrication Challenges.
24. Engineering design of the quasi-poloidal stellarator (QPS).
25. Manufacturing development of the NCSX modular coil winding forms and vacuum vessel.
26. NSTX TF joint failure and re-design.
27. Spherical torus center stack design.
28. ARIES-AT magnet systems.
29. Design of the National Compact Stellarator Experiment (NCSX) core.
30. Design of the Quasi-Poloidal Stellarator Experiment (QPS).
31. Remote maintenance requirements and approach for the FIRE project.
32. Fusion Ignition Research Experiment vacuum vessel design and configuration.
33. Design description of the saddle coils for the National Compact Stellarator Experiment (NCSX).
34. Design of the vacuum liner for the National Compact Stellarator Experiment (NCSX).
35. Design of the plasma facing components for the National Spherical Tokamak Experiment (NSTX).
36. National Spherical Torus Experiment (NSTX) torus design, fabrication and assembly.
37. Next-step spherical torus experiment and spherical torus strategy in the course of development of fusion energy.
38. Drift compression of space-charge-dominated bunched beams.
39. Engineering overview of the ITER hybrid central solenoid.
40. National Spherical Torus Experiment (NSTX) center stack design and assembly.
41. Engineering overview of the National Spherical Torus Experiment (NSTX).
42. Performance of the PBX-M passive plate stabilization system.
43. The TPX cryostat conceptual design.
44. Development and implementation of the TPX structural and cryogenic design criteria.
45. PBX-M upgrade for advanced stabilization and profile control studies.
46. PBX-M vacuum vessel seal upgrade.
47. Testing of TFTR's remote maintenance manipulator.
48. PBX-M passive coil system reliability improvements.
49. Plasma vertical control with internal and external coils in next step tokamaks.
50. The TFTR maintenance manipulator
Catalog
Books, media, physical & digital resources
Discovery Service for Jio Institute Digital Library
For full access to our library's resources, please sign in.