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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.”
E.U. Bashlakova, V.V. Ignatiev, S.V. Kirillov, V.M. Novikov, A.V. Puzirev
Fusion Science and Technology | Volume 20 | Number 4 | December 1991 | Pages 620-626
Advanced Fission Reactors | doi.org/10.13182/FST91-A11946908
Articles are hosted by Taylor and Francis Online.
In providing nuclear power plant safety the priority is currently given to reactor self-protection by means of inherent features and passive means. The problems of self-protection for molten-salt fuel reactor (MSR) and molten-salt cooled coated particle fuel graphite reactor (HTMSR) have been studied. The following ways to reach a high level of self-protection are investigated: a) high level of natural circulation (100% for MSR and 10% for HTMSR); b) integrated layout; c) minimization of reactivity changes during fuel burn-up; d) decrease of maximum operative temperature. Calculations of transient processes during heavy accidents without scram are presented. It is shown that maximum temperatures of the primary circuit materials do not reach critical values under such accidents. For the high hypothetical case with the damage of the reactor and guard vessels in MSR the fission products yield from the fuel salt into gas-phase of MSR containment is investigated.