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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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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.
Dale E. Hankins
Nuclear Science and Engineering | Volume 26 | Number 1 | September 1966 | Pages 110-116
Technical Paper | doi.org/10.13182/NSE66-1
Articles are hosted by Taylor and Francis Online.
The fission yield of an accidental assembly of a supercritical volume of uranyl-nitrate solution will depend on several variables, two of which are discussed here: the rate of reactivity addition, and the effect of the weak-neutron flux in the solution. Fission yields for a 53 g/liter uranyl-nitrate solution subjected to various rates of reactivity addition were calculated. The small number of neutrons from the solution will cause the excursion to occur after the assembly has reached a critical mass and has become slightly supercritical. The effect of the delay in initiation on the fission yield of the assembly is calculated with curves of the probability of initiation vs time. The effect on the fission yield of different neutron source strengths, the addition of sodium carbonate to the solution, and changes in the uranium concentrations of the solutions are discussed. A comparison is made of the predicted values obtained from these calculations and the reported yields from six accidental excursions.