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.”
R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 449-459
Technical Paper | Blanket Engineering | doi.org/10.13182/FST91-A29385
Articles are hosted by Taylor and Francis Online.
Neutronics parameters including the source neutron spectrum, activation rates, and the tritium breeding in the Li2O test zone of the Fusion Neutron Source Phase II experiment performed at the Japan Atomic Energy Research Institute are calculated using the Monte Carlo code MORSE with ENDF/B-V transport and reaction cross sections. Favorable comparisons between the measured and calculated results are achieved for the 27Al(n,α), 58Ni(n,p), 93Nb(n,2n), and 197Au(n,2n) reactions. Calculated 58Ni(n,2n) and 197Au(n,γ) reactions do not agree with measured values within 10 to 40%. For the nickel reaction, the differences may be due to poor data in the ORACT files, while discrepancies for the gold data may be due to unknown quantities of hydrogen-rich epoxy used to coat the Li2CO3 blocks used in the test assembly walls. The calculated tritium breeding in the Li2O agrees with experimental values within ±10% for 6Li and ±15 to 20% for 7Li.