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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.
Yu. E. Titarenko, O. V. Shvedov, M. M. Igumnov, E. I. Karpikhin, V. F. Batyaev, V. I. Volk, A. Yu. Vakhrushin, S. V. Shepelkov, A. V. Lopatkin, S. G. Mashnik, T. A. Gabriel
Nuclear Science and Engineering | Volume 131 | Number 1 | January 1999 | Pages 96-106
Technical Paper | doi.org/10.13182/NSE99-A2020
Articles are hosted by Taylor and Francis Online.
Experimental determination of the resonance neutron absorption in a heavy water solution of 2.57 g/litre 237Np is presented. Experimental samples were irradiated in the MAKET critical plant. Prior to irradiation, 237Np was radiochemically purified to remove 233Pa. The experimental samples were prepared by evaporating two aliquot samples taken from the irradiated solution. The nuclide composition of the samples was analyzed using a GC-2518 Ge detector, a 1510 module, and an S-100 plate to emulate a multichannel analyzer in an IBM personal computer. The spectrometric resolution was 1.8 keV at the 1332-keV line. The gamma spectra were processed by the ASPRO code. The neutron flux was measured by two methods using Al + 55Mn + natCu + 197Au + natLu alloy foils.
