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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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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Nuclear Science and Engineering
September 2025
Nuclear Technology
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August 2025
Latest News
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.
G. Marleau, A. Hébert
Nuclear Science and Engineering | Volume 92 | Number 2 | February 1986 | Pages 240-246
Technical Paper | doi.org/10.13182/NSE86-A18171
Articles are hosted by Taylor and Francis Online.
The interface current method is generally used in supercell codes to accelerate computation of the collision probabilities needed for resolution of the integral neutron transport equation. This method was used to compute all the collision probabilities for a cluster geometry. The resulting complete collision probabilities were then compared with those computed using a direct method. The interface current method was much faster than the direct method for computing collision probabilities, with a loss in precision within the limits of error acceptable for reactor design calculations.
