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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.
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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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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.
W. F. G. van Rooijen
Nuclear Science and Engineering | Volume 162 | Number 3 | July 2009 | Pages 299-306
Technical Note | doi.org/10.13182/NSE162-299
Articles are hosted by Taylor and Francis Online.
The purpose of this technical note is to introduce a definition for breeding gain and other performance parameters for nuclear reactors and their associated fuel cycle. The newly proposed performance parameters have a more general nature than expressions currently in common use. Since the performance parameters require a weighting scheme, which expresses how individual isotopes contribute to the overall fuel cycle performance (breeding, transmutation, or otherwise) of the reactor, expressions are derived for the isotope weight factors. In this technical note, weighting schemes are introduced for a breeding fuel cycle and a transmutation fuel cycle, and the proposed definitions are applied to specific example calculations of a pressurized water reactor mixed oxide irradiation, a breeder reactor cycle, and a transmutation reactor cycle. It will be shown by an example that a net destruction of transuranic material will not always lead to a reduction of the decay heat released from the spent nuclear fuel. This effect is due to the buildup during irradiation of isotopes with a high decay heat release. With the general performance parameters defined in the present work, it is possible to more fully characterize (advanced) nuclear fuel cycles, incorporating long-term radioactivity in a straightforward manner.