ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
E. A. Mogahed, I. N. Sviatoslavsky
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 564-568
International Thermonuclear Experimental Reactor | doi.org/10.13182/FST96-A11962998
Articles are hosted by Taylor and Francis Online.
This paper describes, in part, the design activity related to the ITER limiter first wall (FW). The limiter is needed to protect the reactor FW during plasma startup and shutdown. Steady state heat fluxes of 0.5 MW/m2 are expected with short duration excursions to 5 MW/m2 during startup/shutdown. A 3-D finite element model has been created to represent the beryllium-copper-steel layered construction of the limiter FW. The model takes advantage of the design symmetry, and the large aspect ratio of the limiter which helps in optimizing the finite element model by assuming infinite extent in the poloidal direction. Different options with various boundary conditions are investigated to optimize the limiter FW design and to simulate as close as possible, actual conditions in the limiter. The model is that of a 10 mm diameter hole running poloidally in a Cu block made of GlidCop A125 which is 1.9 cm thick, and the spacing between the hole centers is 2.2 cm in the toroidal direction. The Cu block has a 1 cm thick castellated layer of Be facing the plasma and itself is attached to a cooled SS backing. Each block is discrete with a 1 mm groove separating it from the adjacent block. The interface between the various layers assumes no inter-layer compositions and thus has a singularity due to different material properties. For this preliminary analysis the value of 3.0 MW/m2 heat flux is chosen for reference case. Furthermore, the analysis is elastic, not allowing any plastic deformation. These two rather severe assumptions tend to give higher stresses at the Cu/Be interface. One of the aspects investigated is the depth of the groove in the Cu between the coolant tube blocks. Analysis has shown that when this groove is deeper than 6 mm, the additional effect on the stress at the Cu/Be interface is negligible, the maximum stress in the Cu is reduced, leveling off at a depth of 13 mm. The maximum Be temperature is 552° C and 866° C at the 3 MW/m2 and 5 MW/m2 heat fluxes, respectively. The maximum von Mises stresses at the Cu/Be interface corners are 354 MPa and 679 MPa for the 3 MW/m2 and 5 MW/m2 heat fluxes respectively. These stresses are superficially high due to the stress singularity at the interface and the assumption of no plastic deformation.