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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Jay Basken, Jeffery D. Lewins
Nuclear Science and Engineering | Volume 122 | Number 3 | March 1996 | Pages 407-416
Technical Paper | doi.org/10.13182/NSE96-A24175
Articles are hosted by Taylor and Francis Online.
Accurate solutions of the reactor kinetics equations in a lumped model with time-varying reactivity have been obtained using a spreadsheet on a personal computer (PC)/workstation from a straightforward power series recurrence relation. These have been shown to converge readily over time steps of ∼ s in models of a thermal reactor. Solutions over such macrosteps can readily be extended to durations of interest (∼100 s). Examples are given for both a ramp reactivity input and an oscillating reactivity. This latter shows in a direct fashion the first-order phase distortion and the second-order effect on power level that are generally associated with perturbation solutions that have to be taken to second order. The method applies also to fast reactors. It is concluded that accurate calculations of thermal and fast reactor transients, obtained analytically with considerable difficulty, are readily available to the student on a PC.