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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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May 2025
Latest News
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
John R. Morton III, James M. Piowaty, Joseph Petruzzi, Loren Gardner
Nuclear Science and Engineering | Volume 21 | Number 3 | March 1965 | Pages 289-295
Technical Paper | doi.org/10.13182/NSE65-A20031
Articles are hosted by Taylor and Francis Online.
Reactivity worth measurements are reported for various metal plates in a quasi-homogeneous subcritical assembly of enriched uranium and beryllium oxide. Worths of nickel, iron, cobalt, gold, Hastelloy R-235 and René 41 were measured in this system using the pulsed-neutron method. Equivalences were determined between these absorber materials and the fueled-core material. The results indicate that the prompt lifetime of this system is relatively insensitive to massive localized absorbers.