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Division Spotlight
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.
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.
Sümer Sahin, Ralph W. Moir, Abdulmuttalip ŞAHINASLAN, Haci Mehmet ŞAHIN
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1027-1035
Fusion Blanket and Shield Technology | doi.org/10.13182/FST96-A11963072
Articles are hosted by Taylor and Francis Online.
Material damage through displacements per atom (DPA) and helium gas production, as well as the tritium breeding and energy absorption in an IFE (Inertial Fusion Energy) reactor chamber have been investigated with variable coolant zone thickness using different liquids. Examples are given for HYLIFE-II (an IFE reactor design) energy conversion chambers using Flibe (Li2BeF4), natural lithium and Li17Pb83 cutectic as both coolant and wall protection. To achieve a useful energy density for energy conversion purposes with sufficient tritium breeding (TBR= 1.1), material protection (DPA < 100 and He < 500 appm in 30 years of operation) and shallow burial criteria, coolant zone thickness values are found to be 56 cm for Flibe, 160 cm for natural lithium and 170 cm for Li17Pb83 with SS-304 as structural material.
Material damage investigations are extended to structural materials made of SiC and graphite for the same blanket. DPA values and He production rates in graphite turn out to be comparable to those in SS-304. However, they are higher in SiC, as compared to SS-304 and graphite.