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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.”
Sergei A. Zimin
Fusion Science and Technology | Volume 20 | Number 2 | September 1991 | Pages 144-163
Technical Paper | Shielding | doi.org/10.13182/FST91-A29686
Articles are hosted by Taylor and Francis Online.
The radiation shield for the toroidal field (TF) coils in the International Thermonuclear Experimental Reactor (ITER) is optimized using one-dimensional calculations. The ANISN code with the VITAMIN-C group constant library and MAKLIB-IV response library are used for the calculations. Two ways of evaluating the total heating in the TF coils are presented. These methods, being standard approaches, use the results of both one-dimensional shielding calculations and three-dimensional calculations f or the neutron wall load distribution on the reactor first wall, and they seem to be useful f or future work on ITER and ITER-like projects such as the Next European Torus (NET), Fusion Experimental Reactor (FER), and Compact Ignition Tokamak (CIT). The main results of the optimization and the total heating evaluation are compared with U.S. and European team results. The local nuclear responses in the TF coils remain within the prescribed limits everywhere. The total nuclear heating in the ITER TF coils is within the 50-kW limit in the physics phase using either the U.S. or the USSR blanket concept. The total nuclear heating in the ITER TF coils during the technology phase is expected to be ∼20% lower than that in the physics phase.