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GAIN makes diverse selections for its third round of awards this year
The Department of Energy’s Gateway for Accelerated Innovation in Nuclear has recently awarded four third-round fiscal year 2026 vouchers to support the development of innovative nuclear technologies. Each company will get access to specific capabilities and expertise in the DOE’s national laboratory complex—in this round of awards Idaho National Laboratory, Oak Ridge National Laboratory, and Sandia National Laboratories are named—and will be responsible for a minimum 20 percent cost share, which can be an in-kind contribution.
Don Steiner, Charles A. Flanagan
Fusion Science and Technology | Volume 3 | Number 1 | January 1983 | Pages 6-52
Overview | Fusion Reactor | doi.org/10.13182/FST83-A20816
Articles are hosted by Taylor and Francis Online.
During 1981, the Fusion Engineering Design Center developed a baseline design for the Fusion Engineering Device (FED) called for in the U.S. Magnetic Fusion Energy Engineering Act of 1980. The device has a major radius of 5.0 m with a plasma minor radius of 1.3 m elongated by 1.6. Capability is provided for operating the toroidal field (TF) coils up to 10 T, but the bulk of the operations are designed for 8 T. At 8-T conditions, the fusion power is ∼180 MW (neutron wall loading ∼0.4 MW/m2) and a plasma Q of ∼5 is expected. At 10-T conditions, which are expected to be limited to ∼10% of the total operations, the fusion power is ∼450 MW (∼1.0 MW/m2) and ignition is expected. Maintenance and cost were the key considerations in developing the design. The plasma chamber is assembled by inserting ten shield sectors into a spool support structure. Ten TF coils (7.4- × 10.9-m bore) are employed and produce a 3.6-T field (8 T) or 4.6-T field (10 T) on axis. Options for the TF coils include superfluid-cooled NbTi, subcooled NbTi, and a hybrid coil consisting of both NbTi and Nb3Sn. The poloidal coil system incorporates both normal copper coils (inside the TF coils) and superconducting NbTi coils (outside the TF coils). Plasma bulk heating is accomplished using 50 MW of ion cyclotron resonance heating. Electron cyclotron resonance heating is used for startup assist. A mechanical pumped limiter, located at the bottom of the plasma chamber, establishes the plasma edge and is used to pump hydrogen and helium particles. The first wall consists of water-cooled stainless steel panels complemented with passively cooled graphite armor on the top and inboard walls and on each side of the limiter. The inboard shield is 60 cm thick and the outboard shield is 120 cm thick. Feasible solutions were developed for each of the major systems and subsystems of this FED design. However, key design issues remain, and if resolved could improve the overall design. This design and the supporting basis constitute a departure point for the initiation of a full conceptual design effort.
