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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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.
Robert P. Rulko
Nuclear Science and Engineering | Volume 121 | Number 3 | December 1995 | Pages 371-392
Technical Paper | doi.org/10.13182/NSE95-A24141
Articles are hosted by Taylor and Francis Online.
Historically, the even-order PN equations have been considered a less accurate approximation to the transport equation than the odd-order PN-1 equations. This perception has stemmed from two apparent conceptual difficulties imposed by the even-order PN methods— the difficulty in prescribing rigorous boundary conditions for even-order PN equations that contain the odd number of angular flux moments and the discontinuous character of the even-order PN solutions at material interfaces. With the first one of the mentioned even-order PN conceptual problems, a presentation is made of a straightforward and physically-motivated variational procedure based on a new functional that leads from a multigroup planar geometry transport problem to a multigroup P2 problem with clearly and rigorously defined multigroup boundary conditions. These boundary conditions are new and allow neutron transfer between energy groups at the boundary. These boundary conditions are tested by comparing P2, P1, and SN calculations. Our results show that in the test problems considered, the multigroup P2 equations with variational boundary conditions are always more accurate than the P1 multigroup equations with Federighi-Pomraning or Marshak boundary conditions applied to each energy group.