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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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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.
Mahmoud Z. Youssef, Insoo Jun
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 887-892
ITER Nuclear Design | doi.org/10.13182/FST89-A39806
Articles are hosted by Taylor and Francis Online.
In the initial design of TIBER-II inboard (I/B) shield, multilayers of tungsten shield and coolant were deployed with a total thickness of 48 cm. It was thought during the design process to replace W by PCA. The motivations are: (1) accumulated activation level in the I/B shield at shutdown is larger in the W-shield in comparison to the PCA-shield, and (2) concerns regarding cost/fabrication. This design change required an I/B shield thickness of ∼58 cm to reach the same performance level of the 48 cm W-shield. In this paper a detailed comparison between the two types of shield is given regarding the accumulated radioactivity, biological hazard potential (BHP), and afterheat levels at shutdown and various times thereafter. In addition, a substantial part of the present work is devoted to studying the impact of the present neutron cross-section uncertainties in the prediction of the radiation damage parameters in the S/C magnet. In this regard, an extensive cross-section sensitivity/uncertainty analysis was performed to assess the required increase in the I/B shield thickness in both cases to account for these uncertainties. It was shown that the economic penalty of such an increase is 13–17 M$ in the W-shield case as opposed to 10–14 M$ in the case of the PCA-shield.