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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
George E. Apostolakis
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 141-152
Technical Paper | doi.org/10.13182/NSE74-A23340
Articles are hosted by Taylor and Francis Online.
This is a theoretical investigation of the accuracy of conventional point kinetics in a multiregion reactor without feedback. The fundamental assumption of point kinetics is the splitting of the neutron density into a product of a known constant shape function and an unknown amplitude function. The model cannot acount for the distortion of the shape of the neutron distribution due to space-dependent perturbations and this results in an error in reactivity. It is to this error that bounds are derived. This is done by using the method of weighted residuals to reduce the original eigenvalue problem to that of a real asymmetric matrix. Theorems from matrix algebra are then used to find disks in the complex plane where the eigenvalues are contained. The radii of the disks depend on the perturbation in a simple manner. Examples of space-dependent step and ramp insertion of reactivity in slab reactors demonstrate the usefulness of the bound.