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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
S. Niikura, N. Ueda, I. Yanagisawa, T. Tone, Y. Seki
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 602-607
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40105
Articles are hosted by Taylor and Francis Online.
A computer program system THERMECH for THERmoMECchanical and THERmal-Hydraulic design of fusion blanket has been developed. The THERMECH executes blanket design by following processes: 1) preliminary thermal-hydraulic design of blanket by one-dimensional analysis, 2) pre-processing, calculation, modifying and post-processing of two-dimensional thermal-hydraulic and thermomechanical analyses, 3) pre-processing, calculation and post-processing of three-dimensional thermomechanical analysis, 4) calculation of inelastic strain and resultant stress by one-dimensional analysis. This paper presents the outline of the THERMECH program system and the application to JAERI Tokamak Power Reactor.
