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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.
G. Palmiotti, M. Salvatores
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 333-348
Technical Paper | doi.org/10.13182/NSE87-333
Articles are hosted by Taylor and Francis Online.
Integral experiments play an essential role in the reduction of design uncertainties related to liquid-metal fast breeder reactor neutronics calculations. Spectrum-dependent integral parameters, such as the critical balance, have been the subject of extensive experimental studies in the various critical facility programs of the leading fast reactor programs in view of the extrapolation of the observed results to power reactors. Space-dependent parameters, such as power distribution perturbation and control rod effects, have also been the subject of large experimental programs, but it has been more difficult to find an unambiguous, systematic approach to extrapolate to the reference power reactors with the particular purpose of defining bias factors and uncertainties to be used in design calculations. Different approaches are recalled in the case of spectrum-dependent integral parameters, and some suggestions are made to define a systematic approach for the space-dependent parameters using the existing critical facilities, i.e., reduced-size cores and limited fuel inventories.