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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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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.”
Florent Martinetti, Laurent Donadille, Sabine Delacroix, Catherine Nauraye, Aurélien De Oliveira, Joël Herault, Isabelle Clairand
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 721-727
Proton Therapy | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Protection | doi.org/10.13182/NT09-A9296
Articles are hosted by Taylor and Francis Online.
A Monte Carlo modeling tool was applied at the Institut-Curie Centre de Protonthérapie d'Orsay, France, to simulate the passively scattered beam line used for treatment of ocular melanoma. The primary aim of this study is to validate the model for subsequent calculation of patient doses due to secondary neutrons.The Monte Carlo code MCNPX is used here to model the geometry of the beam line. The beam parameters at the entrance of the ophthalmologic beam line are not well known (beam emittance, lateral distribution, and energy spread). Hence, to accurately implement the beam source in the model, we need to calculate and measure these parameters in the first step of this study. Then, we perform comparisons between calculated and measured proton absorbed dose profiles under various scattering conditions.Comparisons between calculated and measured depth versus dose profiles show discrepancies <0.6 mm (range) and <1.1 mm (beam size and penumbra) for the lateral dose profiles. Hence, calculated relative dose profiles are considered to be correctly described by the Monte Carlo model. Some improvements are still needed to reproduce absolute dose profiles. This study should lead to the use of the numerical model for radiation protection applications.