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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.
V. Rajagopal
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 218-224
Technical Paper | doi.org/10.13182/NSE62-A26060
Articles are hosted by Taylor and Francis Online.
An experimental investigation has been made of the self-fluctuations in neutron density in a nuclear reactor, and the response in neutron density for random reactivity inputs, using analog correlation techniques. The analysis of self-fluctuations was based on ion chamber measurements of the fluctuations of neutron intensity at various points. Autocorrelation analysis was then used to find the power spectrum of the fluctuations, which has the shape of square modulus of transfer function. A random reactivity input was realized by using an electromechanical system to convert the white noise of a radioactive source into linear motion of a small neutron absorber. Analysis of the response was made by autocorrelating the reactivity input and cross-correlating the reactivity input and the response in neutron density, and determining their spectra. The amplitude and phase of the reactor transfer function were determined from these spectra. Results are presented on some measurements made on a small reactor at Brookhaven National Laboratory. The measured transfer function agrees with the calculated transfer function.