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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.
F. Carloni, M. Marseguerra
Nuclear Science and Engineering | Volume 71 | Number 3 | September 1979 | Pages 319-326
Technical Paper | doi.org/10.13182/NSE79-A19069
Articles are hosted by Taylor and Francis Online.
The problem of determining the neutron and count distributions in a multiplying assembly has been independently solved by many authors over the past 30 years. In all cases, the quadratic approximation is used for the probability generating function of the neutrons emitted per fission. In the present paper, this approximation is interpreted as one that almost exactly accounts for the fluctuations of two small samples, one of which is withdrawn from the totality of the neutrons existing at a given time, while the second is taken from all those that have been absorbed up to that time. The observed counts constitute the sample taken from the absorbed neutron population, while the usual distribution of the whole neutron population is obtained from that of the sampled neutrons by performing a suitable change of variable. According to this interpretation, the neutron distribution so obtained may contain rather large errors, and the only case for which we can say that the approximation is safe is that of the count distribution, provided the detector efficiency is kept very small. Indeed, numerical examples show that the relative errors in most cases are of one or two orders of magnitude larger for the neutron distribution than those for the count distribution.