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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.
Antonio F. Dias, Laurance D. Eisenhart, Ronald E. Engel, Lance J. Agee
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 346-358
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2846
Articles are hosted by Taylor and Francis Online.
The rod ejection accident in a pressurized water reactor and the control rod drop accident in a boiling water reactor are analyzed in this paper, both in a best-estimate (realistic) and a conservative manner. CORETRAN, a modern three-dimensional time-dependent nodal code, is used for all simulations. In all considered cases, the resulting peak fuel enthalpy is far less than the current licensing limit of 180 cal/g. The advantage of using a three-dimensional code over the classical point-kinetics approach can be summarized: The power peak is nominally a factor of 10 times lower, and the pulse is 10 times wider. Therefore, a three-dimensional approach predicts a much milder event. Sensitivity studies were performed to identify the influence of several parameters on the reactivity insertion simulations.
