1 / 10

FIRE Engineering

FIRE Engineering. John A. Schmidt NSO PAC Meeting February 27, 2003. Engineering Themes. Develop confidence that the tokamak systems can fit within the established envelopes while meeting the physics requirements Establish a cost estimate that is consistent with the level of design.

sona
Télécharger la présentation

FIRE Engineering

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. FIRE Engineering John A. Schmidt NSO PAC Meeting February 27, 2003

  2. Engineering Themes • Develop confidence that the tokamak systems can fit within the established envelopes while meeting the physics requirements • Establish a cost estimate that is consistent with the level of design

  3. General Status • The magnet systems are the primary space users • The magnet design has a simple configuration and a good basis in past experience and therefore should be reasonably straight forward • However, some R&D will be required to support design • An additional margin has been established for the magnets to provide added assurance that they will fit within their space envelops

  4. General Status 2 • A first cut at allocating the space envelopes for the 2.14 m design has been developed keying off the 2 m design • This allocation will be optimized this summer based on ongoing analysis at the subsystem level • Engineering design development will be needed to support the ongoing AT physics development

  5. Magnets • The stress levels are well balanced between the individual coil systems • 18 % extra margin is remaining for completing the design • Primary issues that remain to be addressed are: • Insulator life • We have a reasonable set of options to choose from • A test program has been developed by MIT • Materials (CuCrZr) that achieve published properties • Improved cooling to increase the pulse rate by about 3

  6. PFC’s • PFC’s will continue to be an issue for burning plasma experiments • The space envelop for the PFC’s is not a large design driver • The design drivers will be: power/pulse length, disruptions and tritium retention • The ITER development of a tungsten divertor plate supports FIRE needs • Remaining issues include: Elm’s, bonding and scale-up of small scale prototypes

  7. Vessel • Disruption analysis must be completed for the 2.14 m design to confirm the vessel thickness (double shell SS306L) • Analysis of the new supporting arrangement for the divertor modules must be completed to assure adequacy of local material thickness • Should we consider ferritic steels?

  8. Diagnostics • Port allocations have been developed • Magnetic diagnostics have a significant impact on the PFC design and therefore these two design must be developed in concert • The integration of specific diagnostics with port shielding must be shown to meet the dose requirements at the ports (neutronics underway) • These port configurations must be shown to be compatible with remote maintenance requirements

  9. FY 04 Plans • Advance the design of FIRE as part of the FESAC Dual Path Strategy, and be prepared to initiate a conceptual design by the time of the U.S. decision on participation in ITER construction • Support both the ITER and FIRE paths of the FESAC Dual Path Strategy: • address generic burning plasma R&D activities (e.g., PFC, disruption mitigation, plasma engineering, insulation development) • continue the development of advanced tokamak scenarios and advanced technologies needed for an attractive tokamak power plant in coordination with ARIES design activities. • facilitate broad community involvement in the US burning plasma initiative

  10. Conclusions • We are well on our way to providing confidence that the tokamak systems will fit within their space envelopes and meet physics requirements. • Small scale R&D and material purchases will be required to support further design development

More Related