ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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.”
B. Tourniaire, O. Varo
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 143-151
Technical Note | Icapp '06 | doi.org/10.13182/NT164-143
Articles are hosted by Taylor and Francis Online.
In case of a pressurized water reactor's severe accident with core meltdown and vessel failure, corium would spread on the concrete basemat of the plant. The high temperature of the corium pool maintained by the residual power would lead to the erosion of the concrete walls and potentially to the bypass of the containment. The ablation velocity of concrete is governed by the heat flux between the corium pool and the concrete wall, and its calculation is of particular significance to predict whether and when the basemat would fail in such a situation. From a hydrodynamic point of view, this issue is related to heat transfer between a volumetric heated bubbling pool and a porous wall with gas injection. Several experimental studies have been performed in the past, and many correlations have been proposed to address this issue. The main purpose of this paper is to assess these correlations from comparisons against the available experimental data. After a review of these data, the different correlations are presented. Attention focuses here on the correlations generally used in molten core-concrete interaction study: The Kutateladze-Malenkov, Konsetov, and BALI correlations. Deckwer's correlation is also included in this review. The comparisons between the results of these correlations and the experimental data are then discussed.