ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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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.”
Marie-Françoise Maday
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 596-601
Fusion Materials | doi.org/10.13182/FST01-A11963302
Articles are hosted by Taylor and Francis Online.
Load-controlled low cycle fatigue tests were carried out on the reduced activation martensitic steel, F82H modified, in pure oxygen-free water at 240°C, thus simulating the most viable coolant chemistry for fusion reactors. It was found that water determined cyclic life reduction as compared to the base-line data in air. Depending on the mechanical parameters employed, the fracture modes were either of the fatigue type and associated with subcritical crack nucleation and stable propagation assisted by the aqueous environment, or almost completely plastic due to the onset of deformation instability which preceded any environmentally-induced cracking process.
The results presented in this paper will be discussed in terms of individual concurrent damaging mechanisms, either time or cycle dependent. Possible causative factors are also suggested for further assessments concerning the cyclic response variability observed in specimens from different lots having, a priori, the same history.