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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.”
Ronald D. Boyd, Sr.
Fusion Science and Technology | Volume 16 | Number 3 | November 1989 | Pages 324-330
Technical Paper | Blanket Engineering | doi.org/10.13182/FST89-A29124
Articles are hosted by Taylor and Francis Online.
Steady-state subcooled water flow boiling experiments were carried out in a uniformly heated horizontal circular channel with an exit pressure of 1.66 MPa and with the mass velocity G varying from 4.4 to 32.0 Mg/m2·s. The test section, which was made of high-strength zirconium-copper, consisted of a tube with an inside diameter of 0.3 cm and a heated length-to-diameter ratio (L/D) of 96.6. The coolant was degassed and deionized water. The inlet water temperature was held constant at 20°C. These experiments are related to high heat flux removal in fusion reactor beam dumps and first walls in compact fusion reactors. For the chosen values of L/D and exit pressure, the measured critical heat flux (CHF) values are higher than any previous values for smooth tubes in the literature. The effect of increasing the pressure from 0.77 to 1.66 MPa is to increase the CHF progressively from 2.0 to 19% as the mass velocity is increased from 4.4 to 25.0 Mg/m2·s. The percent increase in the CHF dropped to 10.0% as G increased from 25.0 to 32.0 Mg/m2·s. Below 25.0 Mg/m2·s, the relationship between the CHF and the mass velocity is linear. Further, an increase in the exit pressure resulted in an increase in the slope of this relationship. However, the local heat transfer coefficient actually decreased as the pressure increased, for the same power level and mass velocity.