ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
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.
L. B. Miller, G. H. Miley
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 438-448
Technical Paper | doi.org/10.13182/NSE70-A20195
Articles are hosted by Taylor and Francis Online.
A Monte Carlo method for the analysis of the Doppler effect has been developed which employs special perturbation techniques to compute effects due to changes in both the temperature and the diameter of fuel rods. These techniques facilitate the application of Monte Carlo to this type of problem and make possible the elimination of approximations inherent in earlier analytic and numerical methods. Numerical results obtained by this method are in good agreement with previously reported measurements on ZPR-III. The method has been applied to the study of the effect of fuel diameter on the Doppler coefficient in a typical fast reactor. Reducing the fuel diameter in a sodium-cooled uranium-carbide reactor from 0.30 to 0.15 cm was found to increase the Doppler coefficient 13%.