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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting 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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WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
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.