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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Reflections on NOW
Hash Hasemianpresident@ans.org
Last month, I talked about my goal of strengthening ANS’s voice, in part by attending three conferences. I have now checked the first event off that list: the Nuclear Opportunities Workshop.
This year, NOW took another step in outgrowing its “workshop” moniker and transitioning to a full-fledged regional conference and expo. What started only a few years ago as a small gathering in Oak Ridge, Tenn., with roughly 50 attendees has skyrocketed to an event with 1,100 people in attendance in Knoxville.
NOW’s popularity reflected how busy the roughly 350 nuclear companies in Tennessee have been in recent years. There is significant work going on surrounding Gen IV reactor development and deployment, advancements in new nuclear fuels, and defense-related builds like the Uranium Processing Facility.
M. Brugger, P. Cennini, A. Ferrari, E. Lebbos, V. Vlachoudis
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 752-757
Heavy Ion Transport | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Measurements and Instrumentation | doi.org/10.13182/NT09-A9301
Articles are hosted by Taylor and Francis Online.
The n_TOF facility, a spallation neutron source, uses a pure lead target to produce neutrons with a 20-GeV proton beam extracted from the CERN Proton Synchrotron. After 4 yr of operation and [approximately]3 yr of cooling, the present spallation target is damaged and was moved to its provisional storage place in the n_TOF service gallery and will be later transferred to a Swiss repository. In this study, to deal with the removal and storage of the lead target, detailed isotope production and residual dose rate calculations were performed with the FLUKA Monte Carlo code. The study further includes a detailed analysis of three-dimensional residual dose rate fields around the target and through the installation pit. It addresses critical design parameters for the new target and successfully compares the simulation results to recently available measurement data. FLUKA allows residual dose rates to be calculated using two different approaches: a one-step approach that simultaneously takes into account production and decay (built-in) and a two-step approach that allows for flexible geometries between the isotope production and sampling of the decay products (customized). This work shows the clear advantage of performing Monte Carlo calculations prior to interventions and waste disposal and the importance of a detailed description of all the installation components, a complete chemical composition inventory, and a correct irradiation profile.