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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.
