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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.
K. Clausen, U. Roose, P. Schneider-Kühnle, F. W. Buchholz, L. Schänzler, S. Stüker, G. Tumbrägel, M. Weinert
Nuclear Science and Engineering | Volume 63 | Number 4 | August 1977 | Pages 493-500
Technical Note | doi.org/10.13182/NSE77-A27063
Articles are hosted by Taylor and Francis Online.
To provide data for testing nitrogen and oxygen cross-section sets, transport of neutrons from a 252Cf source was investigated in a large volume of liquid air. Neutron energy spectra and doses were measured at distances between 30 and 230 cm from the source. Proton recoil proportional counters and NE-213 scintillation detectors were used to obtain energy spectra from 40 keV up to 10 MeV. Different computer programs were employed to unfold the pulse-height spectra. Dose measurements were made using a tissue equivalent ionization chamber and a GM counter. The results are compared with theoretical transport calculations performed with the ANISN code. In general, there is good agreement between the calculations and measurements up to the largest distances.