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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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2024: The Year in Nuclear—July through September
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 July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Cliff B. Davis
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 286-293
Technical Paper | RELAP/MOD2 / Nuclear Safety | doi.org/10.13182/NT90-A34394
Articles are hosted by Taylor and Francis Online.
The possibility of a flow instability in a fuel assembly during a hypothetical loss-of-coolant accident (LOCA) in the production reactors at the Savannah River Site (SRS) is currently the subject of many analyses. The Bingham pumps, which circulate flow through the Savannah River reactors, may be susceptible to cavitation because of the decrease in pressure that accompanies a LOCA. Cavitation in the Bingham pumps during a LOCA could reduce the forced flow through the assemblies and thus could promote flow instability. An analysis was performed at the Idaho National Engineering Laboratory to aid in the evaluation of the potential significance of cavitation on flow instability. The RELAP5 computer code and a model of the L-Reactor at the SRS were the primary analysis tools. A cavitation model was developed using correlations generated at Savannah River and the RELAP5 control system. Benchmark comparisons were performed between the RELAP5 cavitation model and cavitation tests performed in L-Reactor. Best-estimate calculations of a LOCA initiated by a double-ended guillotine break in the inlet piping to the reactor were then performed for a range of core powers. The LOCA calculations were used to determine the initial core power leading to the onset of cavitation and the effects of cavitation on system response. Cavitation was calculated to occur in the broken loop when the initial core power was >1400 MW. Cavitation did not cause a catastrophic reduction in core flow. The effects of cavitation were self-limiting because of feedback among the pump head, loop flow, and the available and required net positive suction head.