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Division Spotlight
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.
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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Jul 2024
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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 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. 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.”
A. Serikov, U. Fischer, D. Grosse, M. J. Loughlin, M. Majerle, S. Schreck, P. Spaeh, D. Strauss
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 708-714
Nuclear Analysis & Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12468
Articles are hosted by Taylor and Francis Online.
Neutronic analyses have been performed assessing the performance of the new radiation shielding design of the upper ports in the Neutral Beam (NB) cell of ITER. The scope of the work includes neutron and gamma spectra and nuclear heating calculations inside the port, as well as assessments of fluences, nuclear heating, and insulator radiation doses in the superconductive magnets in the vicinity of the upper port. For radiation transport calculations, the MCNP5 code has been applied with the Alite 4.1 standard 3D model of ITER, in which the inner structure of the upper port was converted from the underlying CAD (CATIA) data. The conversion has been accomplished by means of the McCad interface code. To address human safety issues, maps of shutdown dose rates have been produced using the Rigorous 2 Step (R2S) method enhanced with the mesh-tally capability. The mesh-based R2S approach couples the MCNP5 mesh-tallies with the radioactive inventory results calculated with the FISPACT-2007 activation code allowing automated calculations of shutdown doses including transport of decay gammas. All results satisfy the ITER radiation design requirements.