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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.
Kohtaro Ueki, Yoshihito Namito
Nuclear Science and Engineering | Volume 96 | Number 1 | May 1987 | Pages 30-38
Technical Paper | doi.org/10.13182/NSE87-A16361
Articles are hosted by Taylor and Francis Online.
Integral shielding experiments using iron-polyethylene slab shields were carried out to determine an optimum arrangement for the neutron dose rate. The total thickness of the iron slabs was fixed at 32 cm, while several thicknesses of polyethylene slabs were employed as a parameter. Some measured data were analyzed by the Monte Carlo code MORSE-CG with the splitting technique. Depending on the location of the polyethylene slab, the measured neutron dose rates changed remarkably in the iron-polyethylene shielding system. When the polyethylene slab was 1 cm thick, the ratio of the maximum neutron dose rate to the minimum value was 1.3, and the ratio was increased to as much as 5.4 for the 14-cm-thick polyethylene slab. The minimum dose point (i.e., optimum shielding arrangement) was observed when the polyethylene slab was located near the detector with the iron slab placed near the neutron source. This was also demonstrated by the Monte Carlo calculations.