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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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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
W. W. Clendenin
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 351-362
Technical Paper | doi.org/10.13182/NSE64-A20055
Articles are hosted by Taylor and Francis Online.
The dependence of the decay time constant of a thermalized neutron pulse in H2O has been calculated both as a function of buckling and of temperature for the range of temperatures between 23 C and 300 C. Fair agreement between results for two moderator models and experiment has been found for the dependence of the diffusion coefficient on temperature. For higher coefficients in the buckling expansion the agreement is poorer. A new iterative method applicable to any moderator model has been used for the solution of the eigenvalue problem. This method is suited to high-order approximations to the transport equation, a P11 approximation having been used in the present calculations. Convergence is rapid. An advantage is that the diffusion-cooled neutron fluxes are given accurately; these are presented and discussed.
