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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
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!
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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.
Karl O. Ott, Robert C. Borg
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 243-261
Technical Paper | doi.org/10.13182/NSE77-A26960
Articles are hosted by Taylor and Francis Online.
An in-depth discussion of the problems of the current description of the growth rate (or doubling time) of breeder reactor fuel emphasizes the need for conceptually improved computational procedures. The presented derivation of improved measures for the growth of breeder reactor fuel is based on a formally correct description of the fast reactor fuel cycle. From these derivations one obtains a hierarchy of four logically different expressions for the fuel growth rate, which yield formally the same value. The first (and most general) definition is obtained by mathematically expressing the doubling time as a measure of the asymptotically exponential growth of fuel in a system of identical breeder reactors. The second definition represents the condensation of the detailed information of the equilibrium fuel cycle analysis for a single reactor. The third growth rate expression is also based on the detailed fuel cycle analysis. Coefficients of an“integrated fuel cycle model” are obtained from the detailed information. This leads to an eigenvalue problem with the growth rate as eigenvalue and the equilibrium plutonium composition as eigenvector. The fourth growth rate expression is based on a set of isotopic weight factors, which is obtained as solution of the adjoint of the fuel cycle eigenvalue problem employed in the third procedure. The resulting “breeding worth factors” are applied to the production and consumption rates of the four plutonium isotopes. This makes the resulting doubling time formula stationary with respect to variations about a reference reactor and practically independent of the fuel composition.