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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.
Kazuo Shin, Ryuji Murakami, Hiroaki Taniuchi, Tomonori Hyodo, Yoshiaki Oka
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 161-171
Technical Paper | doi.org/10.13182/NSE82-A20083
Articles are hosted by Taylor and Francis Online.
Spectral and spatial distributions of neutrons and gamma rays were measured in a simple cavity-duct configuration to observe profiles of cavity streaming. The change of the profiles of neutrons and gamma rays is examined by blocking source neutrons with a 32-cm-thick aluminum plug. The following observations resulted from the experiments: Fast neutrons of several million electron volts energy streamed through ducts. The neutron and gamma-ray spectra were similar except in the source neutron beam. The gamma rays were predominantly those arising from neutron capture in iron. The aluminum plug greatly decreased the fast neutron flux but had only a limited effect on the low energy neutron flux. The applicability of the albedo Monte Carlo calculational method to this problem was examined with the following conclusions: For ducts of small radius, the calculations overestimate the streaming because the albedo data were given for plane geometry. Low energy neutrons were underestimated by the calculation due to the neutron penetration through the cavity wall.