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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.
T. T. Ivanova, M. N. Nikolaev, K. F. Raskach, E. V. Rozhikhin, A. M. Tsiboulia
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 247-255
Technical Paper | doi.org/10.13182/NSE03-35
Articles are hosted by Taylor and Francis Online.
The ABBN-93 299-group cross-section library is used as a source of neutron data for criticality calculations with the MMK-KENO Monte Carlo criticality code. Validation of criticality calculations is performed using the data presented in the "International Handbook of Evaluated Criticality Safety Benchmark Experiments." This paper contains a description of a validation method based on statistical analysis of discrepancies between calculated and benchmark-model keff's and the results of this validation for different types of experiments. Another validation method using a well-known procedure of group cross-section adjustment based on the maximum likelihood method (generalized least-squares method) and results of the validation for water-moderated highly enriched uranium homogeneous critical systems using selected experiments of the HEU-SOL-THERM type are also presented.