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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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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.”
Josselin Morand, Reinhard Hentschel, Andrea Wittig, Raymond Moss, Sabet Hachem, Yuan-Hao Liu, Wolfgang Sauerwein
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 456-461
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9224
Articles are hosted by Taylor and Francis Online.
Monte Carlo simulation of accelerated ions is a standard method in radiation protection. Such simulations have been used to calculate photon and neutron production in a beryllium target of the Essen d(14)+Be Fast Neutron Therapy Facility. In the deuteron case the predominant part of the neutrons is produced by breakup of the input particle, a decay that is not foreseen in standard versions of Monte Carlo codes. Thus, the calculation yields results that are different from measured ones. For simulations of the neutron beam at such facilities, an input description containing the spectral and geometric properties of the neutron and eventually photon beams produced in the target is needed. For the Essen neutron beam, such a description has been obtained by comparison of MCNPX simulations with published data and measurements at a static beam geometry having no background radiation. The validation of the neutron beam input description was obtained by comparing measured and calculated dose distributions in a water phantom using a standard collimator at the treatment gantry.