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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
Fusion Science and Technology
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.
E.T. Cheng, D.K. Sze, J.A. Sommers, O.T. Farmer III
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2001-2008
Safety, Recycling, and Waste Management | doi.org/10.13182/FST92-A30015
Articles are hosted by Taylor and Francis Online.
Materials recycling aspects including contact gamma dose rates and cooling times were investigated for the first wall, blanket, and shield components of future fusion power reactors. Candidate structural mate-rials studied include ferritic steel, vanadium alloy, and SiC ceramic material. Required cooling times to reach hands-on recycling and impurity levels at given cooling times were estimated for the blanket components made of the various candidate structural materials. The relationship between the specific activity limits of radioactive materials for shallow-land burial (U.S. 10CFR61 Class C) waste disposal and the corresponding contact dose rates was examined. Scenarios for waste material management of fusion reactor components were suggested considering the materials recycling and shallow-land waste disposal options. Achievable impurity levels in vanadium ingot and titanium crystal bar were reviewed, and compared to desired levels for hands-on recycling. Methods to improve the purity levels were discussed.
