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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
M. Segev
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 143-152
Technical Paper | doi.org/10.13182/NSE85-A27437
Articles are hosted by Taylor and Francis Online.
A deuterium-tritium neutron source is amplified when emitted into a body of material with appreciable (n,2n), (n,3n), and (n,f) cross sections. This amplification is described by a simple theory, approximating the strict integral transport description of the process. The distribution of neutrons in energy, from 14 MeV down to the (n,2n) threshold, is approximated by a generalized slowing down equation, which is similar in form to the infinite medium slowing down equation, and with average collision probabilities taking up the role of scattering fractions. Following a few collisions, the collision source spatial distribution resembles the fundamental mode flux distribution of a critical reactor. The average collision probability for such a source is, in diffusion theory, ∑tr/(∑tr + DB2), where B2 is the geometrical buckling of the system. This yields an expression of the form (αx+βx2)/(l + αx + βx2) for the average collision probability, where x is a representative optical thickness of the system. It has been shown by numerical means that this form for the average collision probability is generally true for centrally peaked sources in variously shaped bare bodies of any optical thickness.