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Conference Spotlight
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. E. Houghtaling, J. E. Grund
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 412-426
Technical Paper | doi.org/10.13182/NSE69-A18738
Articles are hosted by Taylor and Francis Online.
Reactor kinetics investigations have been performed for cold-start-up, hot-start-up, hot-standby, and operating-power reactivity accidents using the UO2-fueled, pressurized-water type SPERT-III reactor. Power excursion behavior was predicted for every SPERT-III experiment by digital computer calculations using the SPERT-developed PARET code. Extrapolations for severe cold-start-up excursion consequences were obtained from severe transient tests on SPERT-III fuel samples in the SPERT-IV capsule driver core. Analyses of the SPERT-III data show that prompt moderator heating was as significant as the Doppler effect in limiting the magnitude of power excursions in the SPERT-III core at operating temperatures. Comparisons of calculations and experimental data demonstrate that PARET is capable of predicting power excursion behavior in SPERT-III within experimental uncertainty for the range of conditions investigated. The SPERT-III integral-core tests also provide a broad base of experimental data for demonstrations of the capabilities of other existing models in predicting non-damaging power excursion behavior in UO2-fueled reactors.
