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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
Argala Srivastava, K. P. Singh, Amod Kishore Mallick, Umasankari Kannan, S. B. Degweker
Nuclear Science and Engineering | Volume 193 | Number 9 | September 2019 | Pages 1044-1053
Technical Note | doi.org/10.1080/00295639.2019.1596721
Articles are hosted by Taylor and Francis Online.
The use of the Monte Carlo (MC) method for obtaining higher modes is an active area of current research. The method faces several difficulties in its implementation for practical problems. The study of simpler models in this context may be expected to provide insights into some of these problems. This technical note describes the development of a fission matrix algorithm based on the diffusion theory MC model to obtain fundamental and higher λ eigenvalues and eigenvectors (modes) of a reactor. A method for estimating variance in the estimated eigenvalues using first-order perturbation theory is also developed. The algorithm has been implemented in the space-time–kinetics MC code KINMC. The performance of the method for calculating higher eigenvalues and higher eigenvectors has been verified through comparison of the eigenvalues thus obtained with the results of other deterministic codes. Results of computation of eigenvalues and eigenvectors up to six modes are presented in this technical note.