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.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Leading the charge: INL’s role in advancing HALEU production
Idaho National Laboratory is playing a key role in helping the U.S. Department of Energy meet near-term needs by recovering HALEU from federal inventories, providing critical support to help lay the foundation for a future commercial HALEU supply chain. INL also supports coordination of broader DOE efforts, from material recovery at the Savannah River Site in South Carolina to commercial enrichment initiatives.
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.