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

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

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

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

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

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?

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

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

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