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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.
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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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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.”
Zaphar-Ullah Koreshi, Asaf Kinrot, Jeffery D. Lewins
Fusion Science and Technology | Volume 22 | Number 3 | November 1992 | Pages 371-387
Technical Paper | Blanket Engineering | doi.org/10.13182/FST92-A30096
Articles are hosted by Taylor and Francis Online.
The TIBER II blanket design is chosen for a neutronic sensitivity analysis using Monte Carlo perturbation theory. A preliminary analysis is carried out with both deterministic and Monte Carlo simulation codes to estimate the sensitivity of the tritium breeding in the blanket to the atomic density ratio of tungsten multiplier and aqueous solution breeder. Derivatives of the neutron collision density in the blanket are then sampled using the collision estimator in the MORSE code. It is found that for small perturbations, the neutron fluxes and tritium breeding rates can be predicted quite accurately, thus saving substantial computing in a preliminary design study.