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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.”
Yasushi Nomura, Hiroshi Okuno, Yoshinori Miyoshi
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 235-243
Technical Paper | Reactor Safety | doi.org/10.13182/NT04-A3563
Articles are hosted by Taylor and Francis Online.
Simplified evaluation models are developed at the Japan Atomic Energy Research Institute (JAERI) to predict the first peak power, energy, and total fission numbers during a criticality accident for design and installation of a criticality alarm system and for quick response with measures to avoid excessive exposure of the general public. These models were first derived in previous papers only from theoretical considerations employing one-point reactor kinetic neutron behavior and thus are applicable to any geometrical shape of vessel containing fissile solution. Applicability concerning nuclide composition comes essentially from using empirical equations describing specific heat and density to give simplified forms of the models. The models developed originally for a stepwise reactivity insertion mode are shown in the current paper to approximately stand for the ramp reactivity insertion mode by giving their theoretical formation and are validated by applying experimental data from JAERI's Transient Experiment Critical Facility (TRACY) on a low-235U-enriched uranium nitrate solution as well as CRAC experiments on high-235U-enriched uranium nitrate solution together with past accident data, including the most recent JCO accident.