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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.”
Yuan-Zhong Liu
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 192-197
Technical Note | Reactor Safety | doi.org/10.13182/NT98-A2919
Articles are hosted by Taylor and Francis Online.
A 10-MW high-temperature gas-cooled test reactor, the High-Temperature Reactor-10 (HTR-10), being built at the Institute of Nuclear Energy Technology of Tsinghua University, is a type of modular high-temperature gas-cooled reactor. The design features of the HTR-10 are studied in terms of five important sources of airborne radioactive materials released to the environment. These sources are activation of the air in the reactor cavity, leakage of the primary coolant, release of radioactively contaminated helium from the regeneration of the helium purification systems, release of radioactively contaminated helium from the gas evacuation subsystem of the fuel load and unload systems, and leakage of the vapor from the water/steam loops. On the basis of the HTR-10 design parameters, the amount of radioactivity released to the environment per year is calculated, and the dose to the public is calculated as it relates to the HTR-10 site.