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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.
Ernesto C. Vanterpool, Rudolf E. Slovacek, Donald R. Harris, Robert C. Block
Nuclear Science and Engineering | Volume 110 | Number 2 | February 1992 | Pages 186-194
Technical Notes | doi.org/10.13182/NSE92-A23888
Articles are hosted by Taylor and Francis Online.
Interrogation neutrons from 3 eV to 3 keV are used to determine the relative sensitivity of a spent light water reactor fuel assembly assay system. The fuel assay system used for this measurement consists of three threshold fission chambers installed in the Rensselaer intense neutron spectrometer, a 75-t lead slowing-down-time spectrometer at the Gaerttner Linac Laboratory. The fission chambers detect fission neutrons from a simulated fuel assembly, an aluminum enclosure filled with depleted uranium oxide (0.2% 235U), and a 235U (93%) metal foil sample placed at various locations throughout the assembly. The measurements with the assembly are compared with a Monte Carlo analysis of an homogenized pressurized water reactor fuel assembly. This is concluded to be a practical method for the assay of spent fuel.