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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.
Richard F. Mattas
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1487-1492
ITER | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29551
Articles are hosted by Taylor and Francis Online.
The performance of the ITER first wall and divertor have been analyzed using the Fusion Lifetime Prediction (FLIP) code. The code is a one-dimensional finite difference code which calculates the changes in properties, stress, strain, and temperature overtime for plate structures. The results indicate that the first wall should be able to accommodate up to ∼0.6 MW/m2 heat flux for the reference operating conditions. At much higher levels, fatigue and cracking are predicted to lead to rapid failure. The loss of ductility in irradiated austenitic stainless steel at low temperatures is a concern which may limit operating life. The results of the divertor analysis show that a bare, 2 mm thick plate of Nb-1Zr or TZM can accommodate fluxes of 15–20 MW/m2 for the ITER conditions. Duplex structures composed of 2 mm of tungsten on 2mm of Nb-1Zr or TZM are limited to 8–10 MW/m2.
