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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.”
K.G. Porges, M.M. Bretscher
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1903-1908
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29620
Articles are hosted by Taylor and Francis Online.
Measurement of the local breeding rate in a large assembly of fusion blanket candidate materials, irradiated by a fusion neutron source, serves the dual purpose of blanket design support and, perhaps more importantly, of testing analytical methods and cross-section libraries. In this report, we present technical details of a tritium production rate measurement scheme based on the use of neutron irradiation of encapsulated lithium metal samples and subsequent thermal digestion of the samples in a metered carrier hydrogen stream, conversion to THO and LS-counting. A comparison of the scheme to other means of tritium production rate (TPR) measurement with respect to accuracy and other characteristics indicates that its potential accuracy exceeds that of wet-chemistry tritium extraction from lithium salt pellets or TLD deployment and is comparable to the best accuracy of lithium-glass traversing schemes. The sample fabrication and tritium extraction techniques that will be described evolved from well-tested equipment that was previously used in critical (fission) reactor work and cross section measurements, but needed some modification to increase the throughput and thus allow processing the large number of samples required in blanket assay. The applicability of this scheme to measurements at arbitrarily high neutron flux and higher temperatures will be briefly commented on.