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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.
U. Salmi, J. J. Wagschal, A. Yaari, Y. Yeivin
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 298-300
Technical Note | doi.org/10.13182/NSE83-A17799
Articles are hosted by Taylor and Francis Online.
Several widely used neutron transport codes approximate the fission-source matrix by accepting only a single fission-neutron spectrum, regardless of how this spectrum is selected. This approximation introduces a needless calculational error. To overcome this flaw the difference between the correct and the approximate fission source matrices should be added to the scattering matrix. This significantly reduces the calculational errors in integral parameters calculated in the k formulation of the stationary transport equation and eliminates these errors altogether when the integral parameters are calculated in the other formulations of the equation. A numerical example is provided to demonstrate these points. The reactivity k, the average neutron energy , and the ratio are calculated for a JEZEBEL-like assembly using the standard and the proposed procedures.
