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FIRE Engineering

Develop confidence in tokamak systems fitting within envelopes and meeting physics requirements. Establish consistent cost estimate. Magnet systems are primary users with a simple design basis. Stress levels balanced among coils. Diagnostics and vessel analysis imperative for design advancement. Advance FIRE as part of FESAC strategy for ITER participation. Continued R&D activities.

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FIRE Engineering

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  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

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