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.
Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
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.
F. Rahnema, G. C. Pomraning
Nuclear Science and Engineering | Volume 77 | Number 4 | April 1981 | Pages 438-443
Technical Paper | doi.org/10.13182/NSE81-A18956
Articles are hosted by Taylor and Francis Online.
It is well known that for a large reactor a diffusion calculation of the system eigenvalue (criticality) is weakly dependent on the linear extrapolation distance γ. We characterize this weak dependence by a smallness parameter ϵ, and show that the complete neglect of γ leads to an error in the computed eigenvalue of the order of ϵ, whereas the use of an extrapolated endpoint introduces an error of the order of ϵ2. An explicit formula, which preserves the ϵ2 error characteristics, is derived which gives an energy independent extrapolated endpoint in terms of the energy-dependent linear extrapolation distance.