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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
Standards Program
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.
T.A. Khan, D. Tom, R.T. Watts
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 898-903
Tritium | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40148
Articles are hosted by Taylor and Francis Online.
In the design of facilities which handle tritium, radiation safety assessments for various operational parameters and conditions are required. A computer-based system, entitled RAPTIAH, has been developed which performs the analyses and provides the fundamental information required for such assessment. RAPTIAH starts by estimating fluid leak rates from individual components. From the leak rates it derives the rate of tritium release in each area of the facility. Next, the airborne tritium concentrations in areas of the facility and the release of tritium to the environment are obtained. Finally, using component reliability data and the pattern of maintenance, the potential tritium exposure to occupational individuals is estimated. RAPTIAH may be used to identify design measures which would enhance radiation protection in tritium handling facilities.