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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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. Ilieva, T. Apostolov, S. Belousov, Iv. Penev, I. Popova
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 243-247
Technical Paper | doi.org/10.13182/NSE97-A24271
Articles are hosted by Taylor and Francis Online.
Validation of neutron fluence on VVER-440 pressure vessel methodology is performed by comparative analysis of calculational compared with experimental results for the induced activity of scraps taken out from the inner surface of the VVER reactor pressure vessel after the 14th and 17th cycles. The mean deviation of 9% between the experimental and the calculated activity values is evaluated. The good consistency of the results demonstrates the validity of the neutron fluence calculational methodology.
