ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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May 2025
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.
J. T. Dawson, G. Smith
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 125-133
Technical Paper | Technique | doi.org/10.13182/NT82-A16192
Articles are hosted by Taylor and Francis Online.
The Central Electricity Generating Board carries out routine high resolution gamma scanning measurements on fuel discharged from civil advanced gas-cooled reactors in its postirradiation facility at the Atomic Energy Establishment, Winfrith. The measurements yield thermal power density distributions within fuel channels to accuracies of within ±2%, which are used to check the corresponding theoretical predictions and assist the interpretation of postirradiation data. The high precision is achieved by careful attention to detail in both the measurement of fission product count rates and the subsequent analysis, and is demonstrated by internal consistency checks and comparisons with results of independent methods.