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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Young Min Kwon, Chan Eok Park, Jin Ho Song
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 295-305
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2871
Articles are hosted by Taylor and Francis Online.
To investigate the realistic behavior of mass and energy release and resultant containment response during a large-break loss-of-coolant accident (LOCA), analyses are performed on the Yonggwang (YGN) 3&4 nuclear power plants using the RELAP5/CONTEMPT4 computer code. Comparative analyses using conservative design computer codes are also performed. The break types analyzed are the double-ended guillotine breaks at the cold leg and hot leg. The design analysis predicts that the containment peak pressure occurs during the postblowdown phase for the cold-leg break. However, RELAP5/CONTEMPT4 analyses show that the containment pressure has a peak during the blowdown phase, thereafter it decreases monotonously without the postblowdown peak. For the hot-leg break, revised design analysis shows a much lower pressure than that reported in the YGN 3&4 final safety analysis report. The RELAP5/CONTEMPT4 analysis shows a similar trend and confirms that the bypass flow through the broken loop steam generator during postblowdown is negligibly small compared to that of the cold-leg break. In conclusion, realistic analysis by RELAP5/CONTEMPT4 demonstrates that the containment peak pressure occurs during the blowdown phase for both cold- and hot-leg large-break LOCAs, and there is no physical mechanism resulting in mass and energy discharge that can pressurize the containment after end of blowdown for a hot-leg break. Also, it is suggested that the substantial conservatism included in the design analysis should be improved to provide benefits in relaxing the plant technical specifications and reducing the containment design pressure.
