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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.
Yousri Elkassabgi, Graydon L. Yoder, Wallace R. Gambill
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 411-420
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34940
Articles are hosted by Taylor and Francis Online.
The Advanced Neutron Source Reactor (ANSR) is being designed to become the world’s most advanced reactor for neutron scattering research. It is both moderated and cooled by heavy water (D2O) and uses a core of highly enriched uranium silicide fuel in a plate geometry. During the refueling process of the ANSR, the spent fuel must be moved from within the primary coolant loop (containing D2O), through a pool of D2O, and finally into a light water spent-fuel storage area. This is accomplished by using a refueling tunnel and fuel transfer cask or lock. Some means of cooling the core, using either natural circulation or forced convection, must be accommodated during this process. Several thermal-hydraulic aspects of this refueling process have been studied. A modified version of the NATCON computer code developed at Argonne National Laboratory was used for the analysis. The NATCON code was revised and modified to incorporate improved friction and heat transfer correlations, and routines for the physical properties of D2O were added. The revised code can also accommodate a two-dimensional power density distribution. The results for the refueling process design show that ∼48 h is required to ensure the no-boiling condition. The addition of a short chimney reduces that time to ∼12 h.
