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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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Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
Paul J. Turinsky, James J. Duderstadt
Nuclear Science and Engineering | Volume 45 | Number 2 | August 1971 | Pages 156-166
Technical Paper | doi.org/10.13182/NSE71-A20882
Articles are hosted by Taylor and Francis Online.
The substitution of a K-term degenerate kernel expansion (DKE) for the true scattering kernel in the inscattering term for neutron thermalization calculations has been shown to recast the solution of the original speed dependent Fredholm integral operator equation into that of a speed-independent K × K matrix operator equation, which is well suited for numerical calculations: A DKE has been constructed that rapidly converges pointwise to the true scattering kernel, preserves the total scattering cross section, and contains the correct speed structure to yield accurate solutions in neutron thermalization calculations. This DKE was employed in the numerical solution of the steady-state, time-moment, time-eigenvalue, and time-dependent neutron thermalization problems within the framework of asymptotic reactor theory. A detailed numerical investigation of the DKE approximation to the free proton gas and polyethylene scattering kernels indicated that accuracy consistent with a 32 discrete speed mesh point treatment was obtained by employing a 10-term DKE. This implies that the degenerate kernel technique reduces the size of the matrix operator equations to be solved to ∼ ⅓ the size required by a discrete ordinate approach, hence implying considerable computer cost reductions in neutron thermalization calculations.