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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.
K. Behringer, G. Kosály, I. Pázsit
Nuclear Science and Engineering | Volume 72 | Number 3 | December 1979 | Pages 304-321
Technical Paper | doi.org/10.13182/NSE79-A20387
Articles are hosted by Taylor and Francis Online.
According to recent investigations, the neutron noise field in a boiling water reactor can be separated into a local and a global component. In the present paper, these two components are discussed further via two-group diffusion theory. The expediency of the local-global concept is compared to another concept based on separating components corresponding to the two roots of the dynamic eigenvalue problem. The mathematical discussion of the neutron response to a propagating perturbation of the moderator density is given. Point reactor behavior and “linear-phase behavior” appear as two extremes of the neutron response. The mathematical results are illustrated numerically for the cases of a large power reactor core and a small highly enriched core.
