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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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.
G. R. Keepin, C. W. Cox
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 670-690
Technical Paper | doi.org/10.13182/NSE60-A25852
Articles are hosted by Taylor and Francis Online.
The reactor kinetic equations are reduced to an integral form convenient for explicit numerical solution, involving no approximations beyond the usual space-independent assumption. Numerical evaluation is performed by the RTS (Reactor Transient Solution) code, written in FORTRAN II for the IBM-704 computer. The characteristic roots and residues which arise in this method of solution have been computed and are tabulated in detail for each of the main fissile species. Analytic or point-function reactivity variation may be introduced, together with constant or time-varying reactivity compensation, and the resulting power response, total energy release, and compensated reactivity computed precisely as functions of time. The code solves the general non-equilibrium kinetics problem with extraneous sources, the customary equilibrium solution being a special case of the general solution. Practical use of the method is demonstrated through computed response curves for representative reactivity-addition functions in various types of chain-reacting systems.