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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
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2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
Michitsugu Mori
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 205-215
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3025
Articles are hosted by Taylor and Francis Online.
The advanced boiling water reactor (ABWR) has ten reactor-internal pumps peripherally mounted on the bottom of a reactor vessel. Analytical simulation of reactor-internal pumps unique to the ABWR requires new modeling because of the difference in core flow characteristics between the reactor-internal pumps and the two external-recirculation pumps of the primary outer loops with the jet pumps in a current boiling water reactor. Efforts in this work focused on modeling and simulation of reactor-internal pumps and core flow of the ABWR, using the RETRAN-3D code, the computer program for transient thermal-hydraulic analysis of a complex fluid flow system, without multidimensional kinetics. Included are modeling of the core and reactor pressure vessel with ten reactor-internal pumps, and simulation of the events of reactor-internal-pumps trip during the startup-phase tests, which are unable to be done in the simulation of a current BWR. Sensitivity analyses on the recirculation flow control and the slip model were also performed. The predictions by the RETRAN-3D code successfully tracked the measured data of reactor-internal-pump trip during the startup-phase test. The present analytical simulations could demonstrate the validation of the RETRAN-3D code applicable to the ABWR with the pump model of reactor-internal pumps in the program.