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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.