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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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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.”
Yuezhou Wei, Tsuyoshi Arai, Harutaka Hoshi, Mikio Kumagai, Aimé Bruggeman, Patrick Goethals
Nuclear Technology | Volume 149 | Number 2 | February 2005 | Pages 217-231
Technical Paper | Reprocessing | doi.org/10.13182/NT05-A3591
Articles are hosted by Taylor and Francis Online.
We have studied a new aqueous reprocessing system that consists of anion exchange as the main separation method, electrolytic reduction for reducing U(VI) to U(IV), and extraction chromatography for minor actinide partitioning. In this work, hot tests were carried out on the main flow sheet (U and Pu recovery) using a nitric acid solution of a spent commercial boiling water reactor fuel with burnup of 55 000 MWd/t HM. First, a separation experiment was conducted using a column packed with AR-01 anion exchanger, and the separation behavior of about 20 elements was examined. Then electrolytic reduction was performed for the U(VI) eluate from the first column using a flow-type electrolysis cell. Subsequently, the reduced U solution was applied to the second AR-01 column to separate the U(IV) from contaminated fission products. Most amounts of Pu(IV)-Np(IV), were successfully separated and recovered in the first column. In the electrolysis, U(VI), Np(V,VI), and a trace amount of Pu(VI) were reduced to U(IV), Np(IV), and Pu(IV), respectively. In the second column, the U(IV) with small amounts of Np(IV) and Pu(IV) was completely separated from the fission products. These results demonstrated that the proposed U and Pu recovery process is essentially feasible, though more effective elution methods for Pd and Tc need to be investigated further.