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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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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.
Gerald Kamelander
Nuclear Science and Engineering | Volume 83 | Number 4 | April 1983 | Pages 507-513
Technical Note | doi.org/10.13182/NSE83-A18656
Articles are hosted by Taylor and Francis Online.
The Monte Carlo theory provides a powerful tool for solving three-dimensional neutron shielding problems. Special variance reducing methods must be applied if the detector regions are very remote from the source region. Recently, an idea for a new scoring method was proposed to reduce an estimator for large distances between flux point and collision point to the standard flux point estimator. A Monte Carlo code based on this method was developed. This code was applied to the calculation of neutron doses, neutron spectra, and neutron fluxes produced by the detonation of an enhanced radiation weapon. The results may be considered as a test of the efficiency and as a first application of a new Monte Carlo method. The radiation doses reported in this Note only refer to neutrons. The gamma-ray radiation doses due to neutron capture reactions are not considered.