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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
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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.
Alberto Talamo, Yousry Gohar, H. Kiyavitskaya, V. Bournos, Y. Fokov, C. Routkovskaya
Nuclear Technology | Volume 184 | Number 2 | November 2013 | Pages 131-147
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A22310
Articles are hosted by Taylor and Francis Online.
This study compares Monte Carlo and deterministic neutronics analyses of the zero-power YALINA Thermal subcritical assembly, which is located in Minsk, Belarus. The YALINA Thermal facility consists of a subcritical core that can be driven by either a californium neutron source or a deuterium-deuterium (D-D) neutron source. The californium neutron source is generated by the natural decay of 252Cf; the D-D neutron source is generated by a deuteron accelerator. The MCNPX, MONK, NJOY, DRAGON, PARTISN, and TORT computer programs have been used for calculating the neutron spectrum, the neutron flux, and the 3He(n,p) reaction rate set by californium and D-D neutron sources. These parameters have been computed in different experimental channels of the assembly for different fuel loading configurations. The MCNPX and MONK computer programs modeled the facility without any major approximation; the PARTISN and TORT computer simulations used 69 energy groups, S16 angular quadrature set, linear anisotropic scattering, and approximately 60 homogenized material zones. The results calculated by different computer programs are in good agreement; in addition, they match the 3He(n,p) reaction rate from experimental measurements obtained by californium and D-D neutron sources.
