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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Linda D. Vickers
Nuclear Science and Engineering | Volume 145 | Number 3 | November 2003 | Pages 354-375
Technical Paper | doi.org/10.13182/NSE03-A2388
Articles are hosted by Taylor and Francis Online.
This paper provides the radiation absorbed dose rates (rad-h-1) to a tissue-equivalent torus ring at 1 meter from radioactive spallation products in Ta, W, Pb, Bi, and LBE target materials used in Accelerator Transmutation of Waste (ATW) applications. No previous works have provided an estimate of the absorbed dose rates (rad-h-1) to tissue from activated targets for ATW applications. In addition, this paper provides the characterization of target materials of high-energy particle accelerators for the parameters of (a) spallation neutron yield (neutrons/proton), (b) spallation products yield (nuclides/proton), (c) energy-dependent spallation neutron fluence distribution (n-cm-2 MeV-1), and (d) identification of the optimal target dimensions to yield the maximum radial spallation neutron leakage from the target. A beneficial characteristic of these target materials (Ta, W, Pb, Bi, and LBE) is they do not produce radioactive transuranic isotopes, which have very long half-lives and require special handling and disposition controls. In addition, these activated, spent targets are not considered high-level radioactive waste for disposal purposes such as spent fuel from a nuclear power reactor.
