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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.
William L. Woodruff
Nuclear Technology | Volume 64 | Number 2 | February 1984 | Pages 196-206
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33342
Articles are hosted by Taylor and Francis Online.
The PARET code, originally developed for the analysis of the SPERT-III experiments for temperatures and pressures typical of power reactors, has now been modified to include a selection of flow instability, departure from nucleate boiling, single- and two-phase heat transfer correlations, and a properties library considered more applicable to the low pressures, temperatures, and flow rates encountered in research reactors. The PARET code provides a coupled thermal, hydraulic, and point kinetics capability with continuous reactivity feedback, and an optional voiding model that estimates the voiding produced by subcooled boiling. This modified code has been adapted for the testing of methods and models and for subsequent use in the analysis of transient behavior in research reactors. Comparisons have been made with the experimental results from the SPERT-I transients, and the agreement with the experimental data is generally quite good. The selection of proper correlations and properties for the range of interest in research reactors was essential to the accuracy of the results. The code has also been applied to the analysis of the International Atomic Energy Agency 10-MW benchmark cores for protected and unprotected transients. The code provides an accurate capability for the analysis of research reactor transients. This modified version of the PARET code is available through the National Energy Software Center.
