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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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Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
M. E. Rensink, T. D. Rognlien
Fusion Science and Technology | Volume 67 | Number 1 | January 2015 | Pages 125-141
Technical Paper | doi.org/10.13182/FST14-800
Articles are hosted by Taylor and Francis Online.
Simulations of the heat flux on plasma-facing components from core exhaust plasma are reported for two possible ACT1 divertor configurations. One configuration uses divertor plates strongly inclined with respect to the poloidal magnetic flux surfaces similar to that planned for ITER and results in a partially detached divertor plasma. The second configuration has divertor plates orthogonal to the flux surfaces, which leads to a fully detached divertor plasma if the width of the divertor region is sufficient. Both configurations use scrape-off layer radiation from seeded impurities to yield an acceptable peak heat flux of ∼10 MW/m2 or smaller on the divertor plates and chamber walls. The simulations are performed with the UEDGE two-dimensional transport code to model both plasma and neutral components with some supplementary neutral modeling performed with the DEGAS 2 Monte Carlo code.