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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.
A. Alberman, G. Bley, P. Pépin, P. Soulat
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 639-646
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33485
Articles are hosted by Taylor and Francis Online.
Within the framework of the high-temperature gas-cooled reactor (HTGR) R&D agreement with GA Technologies, Inc., the Centre d’Etudes Nucléaires de Saclay investigated the transition temperature shift of the liner steel exposed to (thermal) neutrons. The steel was ferritic A537 (1.32% manganese, 0.26% copper, 0.26% silicon, 0.21% nickel, and 0.14% chromium). The specimens were irradiated in the French EL3 heavy water research reactor in an area where the neutron spectrum was comparable to that occurring in front of the HTGR core cavity liner:Φth/Φƒ ∼ 1000 . The temperature was 60 °C during the irradiations. For theoretical purposes, two irradiations were carried out at two different fluences. In addition, some specimens were cadmium plated to examine the effect of fast neutrons. Charpy impact tests were performed at Saclay with an instrumented impact device. The results show that current models overestimate the thermal neutron effect by a factor of 3.