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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.
W. K. Hagan, B. L. Colborn, T. W. Armstrong, M. Allen
Nuclear Science and Engineering | Volume 98 | Number 3 | March 1988 | Pages 272-278
Technical Note | doi.org/10.13182/NSE88-A22328
Articles are hosted by Taylor and Francis Online.
Neutron shielding calculations for a 70- to 250-MeV proton cancer therapy facility have been carried out using the High Energy Transport Code and the one-dimensional discrete ordinates code ANISN. Calculations were performed for iron and water targets with incident proton energies of 150, 200, and 250 MeV. The angular dependence of the neutron spectrum was taken into account by averaging and reporting the spectrum in angular bins of 0 to 15, 15 to 30, 30 to 45, 45 to 60, 60 to 90, and 90 to 180 deg relative to the forward direction of the protons. Each of these various spectra was used as the source spectrum for an individual ANISN run in which the source was placed at the center of a sphere of typical concrete (i.e., density of 2.3 g/cm3) and the dose equivalent per proton was calculated as a function of radius. These calculations differ from previous work primarily in the method used to calculate the neutron spectrum due to the interaction of the protons with the target and the transport cross sections used in the ANISN calculations.