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Conference Spotlight
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.
A. Hébert
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 34-58
Technical Paper | doi.org/10.13182/NSE85-A17127
Articles are hosted by Taylor and Francis Online.
A number of improvements have been made to the Hermite method in order to obtain a high order finite element method capable of solving the neutron diffusion equation. First, a variational formulation of the equation is used to obtain a Weierstrass-Erdmann-type coupling relation valid at all points in the domain, singular and nonsingular. The basic solution yielded by this type of discretization is obtained by the inverse power method with variational acceleration of outer iterations. The linear systems appearing in the inverse power method are solved using a one-way dissection algorithm followed by asymmetric block factorization. These procedures were programmed in the BIVAC code for a treatment of the neutron diffusion equation with a two-dimensional reactor representation. The Hermite method was then compared with alternative approaches to a solution. The tests correspond to two-dimensional configurations of pressurized water reactors and CANDU reactors.