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Division Spotlight
Reactor Physics
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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Seong-Wan Hong
Nuclear Technology | Volume 167 | Number 1 | July 2009 | Pages 211-222
Technical Paper | NURETH-12 / Thermal Hydraulics | doi.org/10.13182/NT09-A8863
Articles are hosted by Taylor and Francis Online.
Sustained heating experiments, named Experiments on Late-phase coolant Injection to ASsess the mitigation of focusing effect of metallic layer (ELIAS), were performed to quantify the boiling heat removal rate at the upper surface of a metallic layer for precise evaluations on the effect of a late-phase in-vessel coolant injection. Heat fluxes from the melt layer to the water pool varied from 250 to 550 kW/m2 depending on the surface temperature of the metallic layer. Comparison of boiling heat fluxes between the ELIAS experiments and the calculation using Berenson's film boiling correlation shows that effective heat removal was accomplished via late-phase coolant injection in the ELIAS experiments. In this study, a simple model was developed to evaluate the mitigation of focusing effect in the metallic layer via late-phase coolant injection. The ELIAS experimental data on the heat transfer rate at the upper surface of the metallic layer were used as input data in the simple model. The calculation results for the large-break loss-of-coolant accident in the APR1400 show that the risk induced by the focusing effect is highly dependent on the metallic layer thickness and an enhanced integrity of the reactor pressure vessel could be achieved via late-phase coolant injection during this time period.