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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.
G. C. Pomraning
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 325-330
Technical Paper | doi.org/10.13182/NSE91-A23831
Articles are hosted by Taylor and Francis Online.
Within the context of one-group diffusion theory, we discuss the effect of randomness (stochasticity) on the criticality of a bare nuclear reactor. Previous authors have concluded that randomness decreases the critical size for a given amount of fuel, and that such randomness, when in-troduced into a homogeneous critical reactor, leads most probably to a supercritical state. By considering a sufficiently simple stochastic problem so that exact results can be obtained, we judge these prior conclusions to be only partially correct. We show that the effect of randomness on a criticality problem depends on both the nature of the randomness and the ensemble-averaging procedure and interpretation used to describe the reactor in the stochastic setting.