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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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DOE-EM awards $74.8M Oak Ridge support services contract
The Department of Energy’s Office of Environmental Management has awarded a five-year contract worth up to $74.8 million to Independent Strategic Management Solutions for professional support services at the Oak Ridge Office of Environmental Management site in Oak Ridge, Tenn.
D. R. Harris, M. Natelson, J. A. Galey, E. Schmidt
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 173-198
Technical Paper | doi.org/10.13182/NSE70-A19681
Articles are hosted by Taylor and Francis Online.
Correlated neutron fluctuation experiments have been performed on a poorly coupled, multiple seed-blanket reactor and on a better coupled cylindrical lattice reactor. The fluctuating numbers of counts recorded in various gate times by separated detectors are analyzed in terms of a proposed measure of reactor coupling, the modified coefficient of correlation, MCC, as well as in terms of the conventional dispersion parameter Y. Effects of count losses, statistical bias, and statistical error are examined. Calculations of MCC and Y are carried out in the α-mode form of the product density formalism for a number of detailed reactor models, including several four-energy-group diffusion theory and P-3 transport models for reactor design. Two of these detailed models, incorporating reduced fast-neutron transport and removal cross sections, are in agreement with MCC measurements, while one design model is not.