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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.
Daniel López, Javier Sanz, Francisco Ogando
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 252-257
IFMIF | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14143
Articles are hosted by Taylor and Francis Online.
During the IFMIF/EVEDA phase, a 125 mA and 9 MeV deuteron prototype accelerator will be designed and tested for the final IFMIF project. Deuteron losses will occur during operation of the accelerator at several components as well as at the beam stopping, leading to material activation induced by deuterons and/or by secondary neutrons, depending on the location. This work is focused on the residual dose rate assessment inside the accelerator vault due to the radioactive inventory induced in the main accelerator components, the outside concrete structures of the accelerator vault, and the concrete-made local shielding of the beam dump. The results will be useful for maintenance work planning, identifying hot areas in the accelerator region. The adopted computational procedure uses MCUNED for determination of spatial distribution of deuteron and neutron fluxes, ACAB for activation calculations, and MCNPX for transport of decay gammas. Deuteron transport cross sections are taken from TENDL-2010 and decay and activation cross-section data from EAF-2007.