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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Latest News
IAEA again raises global nuclear power projections
Noting recent momentum behind nuclear power, the International Atomic Energy Agency has revised up its projections for the expansion of nuclear power, estimating that global nuclear operational capacity will more than double by 2050—reaching 2.6 times the 2024 level—with small modular reactors expected to play a pivotal role in this high-case scenario.
IAEA director general Rafael Mariano Grossi announced the new projections, contained in the annual report Energy, Electricity, and Nuclear Power Estimates for the Period up to 2050 at the 69th IAEA General Conference in Vienna.
In the report’s high-case scenario, nuclear electrical generating capacity is projected to increase to from 377 GW at the end of 2024 to 992 GW by 2050. In a low-case scenario, capacity rises 50 percent, compared with 2024, to 561 GW. SMRs are projected to account for 24 percent of the new capacity added in the high case and for 5 percent in the low case.
J.H. Schultz, D.B. Montgomery
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1019-1024
Next-Generation Devices | doi.org/10.13182/FST83-A22992
Articles are hosted by Taylor and Francis Online.
Alcator DCT is an experimental tokamak proposed to be built at M.I.T. It features extremely long pulses, RF heating and current drive, and an all superconducting magnet system. The toroidal magnets produce a field on-axis of 7 T, permitting current drive at high density and ion heating with existing power supplies. The device is designed to maximize the use of existing facilities at M.I.T. in order to build a machine large enough for simultaneous heating and current drive at low cost. This report concentrates on a design option with 24 circular toroidal field (TF) magnets, which represents the second iteration in the conceptual design of this machine. This design is a modification of the HESTER concept developed by the authors1, The DCT design is an advance over the HESTER design, in that it has adequate horizontal port space for human access and for tangential viewing of the plasma at the geometric center. This was achieved by decreasing the number of TF coils from 36 to 24. increasing the magnet bore from 52 to 62 em and shaving diagonals from noncritical areas of the case in the lead and header region. Recent perceptions of the requirements of the tokamak program in the areas of impurity control and in-vessel component screening indicate that a third significant iteration of the DCT concept is necessary. The Alcator DCT uses pumped limiters for long term impurity control. Doubts about the efficacy of pumped limiters and a desire to concentrate on long-term impurity control issues led to the recommendation that DCT be modified to include expanded boundary and simplified poloidal divertor operation. Early work on these options is described briefly.