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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Nuclear Science and Engineering
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Nuclear Technology
July 2025
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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.
H. Giese, S. Pilate, J. M. Stevenson
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 262-282
Technical Paper | doi.org/10.13182/NSE84-A17782
Articles are hosted by Taylor and Francis Online.
Measurements of the worths of simulated control rods for fast power reactors have been made in the ZEBRA and SNEAK critical assemblies by the modified source multiplication method (MSMM). The assemblies used were the conventional and unconventional core arrangements from the BIZET program and a compacted version of a conventional core. The control rods were mainly natural B4C, with some study of 40% 10B-enriched B4C and of Eu2O3. Correction factors for the MSMM were obtained from eigenvalue and source-mode diffusion theory calculations in XY geometry. The measured rod worths and interactions are compared with calculated values from methods and data similar to those used by the different participants in the BIZET program to predict the corresponding parameters in fast power reactors. In general, acceptable agreement is found.
