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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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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.
Michitsugu Mori
Nuclear Technology | Volume 148 | Number 1 | October 2004 | Pages 12-24
Technical Paper | RETRAN | doi.org/10.13182/NT04-A3544
Articles are hosted by Taylor and Francis Online.
Two advanced boiling water reactors (ABWRs) whose electric output power is 1356 MW have been commercially operated since 1996 and 1997 by the Tokyo Electric Power Company (TEPCO) in Japan. Features of an ABWR are reactor internal pumps (RIPs) placed in the lower plenum and downcomer, peripherally bottom-mounted on the reactor pressure vessel - which should require different modeling from the jet pumps and two recirculation pumps in the primary outer-loop recirculations of BWR-5.Efforts focused on modeling and simulating the ABWR with transient analyses by the point-kinetics model with the local reactivity modified by local importance weighting of the squared nodal power during start-up tests using the RETRAN-3D code, version MOD003 without three-dimensional kinetics. The core and reactor pressure vessel including ten ABWR RIPs and the steam lines were modeled, and simulations were carried out for the cases of the one-pump trip test, the changing-setpoint tests, the main-steam-isolation-valve-closure test, and the generator load rejection test with bypass.The analytical simulation with RETRAN-3D/MOD003 well reproduced the measured data of the ABWR in operation for the RIP trip and the transient tests and could demonstrate its validation for applying to the ABWR with modeling of RIPs.