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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.
J. V. Siebers, P. M. DeLuca, Jr., D. W. Pearson, R. E. Prael
Nuclear Science and Engineering | Volume 122 | Number 2 | February 1996 | Pages 258-266
Technical Paper | doi.org/10.13182/NSE96-A24160
Articles are hosted by Taylor and Francis Online.
Shielding related calculations were performed for 230-MeV protons incident upon a stopping-length iron target using the LAHET code system (LCS). Secondary neutrons and photons, produced by proton interactions with the target nuclei, were transported through a spherical concrete shield in which absorbed dose and dose equivalent tallies were produced and attenuation parameters deduced. Comparing calculated results with measurements performed with a similar target, beam, and shielding geometry, the dose equivalent production term is double the measured value. The LCS overestimates measured attenuation values at 0, 22, and 45 deg while correctly predicting the attenuation length at 90 deg. Comparisons of LCS results with HETC calculations and analytical methods indicates that LCS better estimates the attenuation length and dose equivalent production.