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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.
Michael Scott McKinley, Farzad Rahnema
Nuclear Science and Engineering | Volume 136 | Number 1 | September 2000 | Pages 15-33
Technical Paper | doi.org/10.13182/NSE00-A2145
Articles are hosted by Taylor and Francis Online.
A perturbation method is developed for estimating the change in the solution of a reactive system to any order for a perturbation in the boundary condition in diffusion theory. The method derived gives formalisms for the eigenvalue, normalized flux, and homogenized parameters. Five examples are provided to verify the method as well as analyze the errors associated with it. The first example is very simple and solves the state of the system up to eighth order and gives a simple numerical analysis of a large perturbation. The next example gives an analytical solution up to second order. A two-region example is also given, which is partially numerical and partially analytical. An albedo test example shows that the higher-order terms all appear to be present in the formalism. The final example presents a simplified one-dimensional boiling water reactor core analyzed up to third order numerically. Applications of this method, error propagation, and future work are also discussed.