FIRE Engineering

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 RD 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
PFCs

• PFCs will continue to be an issue for burning
  plasma experiments
• The space envelop for the PFCs 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 Elms, 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 RD 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 RD and material purchases will be
  required to support further design development