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
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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.”
Leah Spradley, Mark Abkowitz, James H. Clarke
Nuclear Technology | Volume 170 | Number 2 | May 2010 | Pages 322-335
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT10-A9486
Articles are hosted by Taylor and Francis Online.
This research estimates the likelihood of the number of occurrences of three internal events involving crane transfers during the potential 50-year preclosure operational period of Yucca Mountain (YM): (a) drop of a bare-fuel assembly, (b) drop of a transport, aging, and disposal canister, and (c) drop of a dual-purpose canister. The analysis employs a model developed by the authors for predicting the packaging and thermal characteristics of waste streams arriving at YM and is related to a study on throughput for the surface facilities that was also conducted by the authors using the model. The model generates waste streams for commercial spent nuclear fuel as a function of repository design parameters and operating strategies.Waste streams arriving at the repository are assumed to be routed for processing in the surface facilities based on the thermal properties of the packages. This allows for estimation of the number of material crane transfers associated with each waste stream. The number of drops over the preclosure period is described as a binomial distribution, where each crane transfer is treated as an identical, independent trial with an outcome of drop or no drop.Results indicate that the drop events are not expected to occur one or more times during the preclosure operational period. This paper demonstrates an approach for estimating the likely distributions for frequencies of drop events, accounting for uncertainty in waste stream quantities in addition to changing assumptions about the crane drop rate. While it is recognized that results of this analysis are specific to YM surface facility design, the approach can be adapted for similar systems designed for centralized interim storage.