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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Prepare for the 2025 Nuclear PE Exam with ANS guides
The next opportunity to earn professional engineer (PE) licensure in nuclear engineering is this fall, and now is the time to sign up and begin studying with the help of materials like the online module program offered by the American Nuclear Society.
R. A. Danofsky
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 28-38
Technical Paper | doi.org/10.13182/NSE69-A18854
Articles are hosted by Taylor and Francis Online.
A space-dependent noise formulation is developed on the basis of the modal-analysis technique. Application of the method is illustrated by numerical calculations carried out for a one-dimensional model of a coupled-core Argonaut type reactor. It has been found that the suggested method may be readily used to calculate the auto- or cross-spectral-density functions of the neutron-level fluctuations for any of the group fluxes of a multienergy group calculation when the system is subjected to arbitrary stochastic input functions. Results obtained from the numerical calculations serve to illustrate the importance of the space dependence of the spectral functions and in particular the sensitivity of the cross-spectral-density function to the two points of observation.