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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.
Wolfgang K. E. Braun, Klaus Hassmann, Hans-Henning Hennies, J. Peter Hosemann
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 268-290
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor | doi.org/10.13182/NT86-A33766
Articles are hosted by Taylor and Francis Online.
A survey of the engineered design of the containment of a standard German pressurized water reactor of the 1300-MW(electric) category is presented. One essential part of the containment consists of a 4-cm-thick and 56-m-diam detached steel shell, surrounded by a 2-m-thick concrete shielding. Between the concrete shell and the containment, an annulus has been provided that can be vented via filters under accident conditions. In numerous experiments, the extraordinarily conservative approach in the layout of the structure has been proved to withstand the loss-of-coolant design-basis accident. This conservative approach in design also has positive effects in restricting the consequences of a core meltdown accident.
