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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Pierre Saunier (CEA), Franck Peysson, Denis Etienne (BOUYGUES Construction), Vincent Le Talbodec, Laurent Dufrene (CNIM)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 667-674
The French Generation IV sodium cooled Fast Reactor (SFR) is designed with a large pool-type vessel and equipment (pumps, heat decay removal) which are sensitive to horizontal seismic accelerations. It is necessary to design these components with an appropriate seismic isolation system depending on the site seismic conditions.
For ASTRID, the SFR industrial demonstrator project under development by the CEA, the preliminary study has concluded to the necessity to isolate horizontally all the buildings of the nuclear island on a para-seismic raft equipped with seismic pads. At the current Basic Design phase, the project takes into account the lessons learnt from the recent Jules Horowitz Reactor (JHR) and ITER research reactor projects under construction and equipped with seismic isolators.
Seismic isolation allows to decrease the horizontal building accelerations from 5 to 10 times. Positive aspects consist in reducing the average reinforcement ratio of these buildings and to ease the design of the main reactor block components, with in the end, an expected gain of cost.
ASTRID partners aims also to improve and innovate with this isolation technology. Based on the European standards, previous solutions used elastomeric rubber with metallic parts pads. BOUYGUES Company (CEA’s partner for ASTRID), associated to CNIM Company, has chosen to change the raw material, using polyurethane material instead of natural rubber. Several advantages are expected. With ageing, the polyurethane is softening whereas natural rubber is hardening (and potentially reducing seismic isolation capacity).
The main conclusion is that these new pads respect the dynamic behavior of the buildings, give better margin in seismic condition and allow modifying easily the pads stiffness.
The next step is that a complete qualification program will be implemented in order to validate the one scale dynamic characteristics of the isolators at full scale and to justify the requested 90 years lifetime.