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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.
A Aytekin, V Corcoran
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1463-1468
Tritium Waste Management and Discharge Control | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30618
Articles are hosted by Taylor and Francis Online.
A Gas Clean Up System (GCUS) has been designed, built and installed for the new tritium handling facility at Atomic Weapons Establishment (AWE), Aldermaston. The system is in the process of being commissioned and once this is complete and the facility is operational, it will be used for the removal of hydrogen isotopes from gaseous waste arisings within the facility and concentrating them in waste packages. The system also provides a depression for the sources of these waste arisings, particularly the inert gas gloveboxes, as part of the contamination containment within the facility. This paper describes the details of various sub-systems within the GCUS and their engineering, construction, installation and testing.
