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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
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.
Mahmoud Z. Youssef, Russell Feder, Kelly Thompson, Ian Davis, Gregory Failla
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 718-725
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8993
Articles are hosted by Taylor and Francis Online.
The new feature of the ATTILA 3-D code to calculate dose rates in a given geometry was benchmarked using the dose rate experiments performed at the FNG 14.1 MeV source facility located at ENEA, Frascati, Italy. Two experimental campaigns were performed. Post irradiation measurements were undertaken using Geiger-Müller, TLD, and tissue-equivalent scintillators. Other measurements were also performed during irradiation. ATTILA results were compared to the experimental data and to the results of the MCNP Monte Carlo code published earlier. The calculations were performed through three consecutive steps using the same ATTILA code along with its built-in activation library, FORNAX. The ANSI/ANS6.1.1-77 and ICRP74 Ka flux-to--dose conversion factors were used. Good agreement with the experimental data and the MCNP results was obtained for times >7 d after irradiation in the 1st campaign but large underestimation was found at shorter time steps. Both dose rates and integrated gamma fluxes are largely underestimated (∼20-40%) in the 2nd campaign.