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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
Ryohei Tanaka, Tatsuo Kondo
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 75-87
A. Selection, Production, and Development of Alloys for HTGR Component | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33457
Articles are hosted by Taylor and Francis Online.
The developments of the last decade are reviewed on a technical basis for heat-resistant alloys in application to the high-temperature structural components of the process heating high-temperature gas-cooled reactor. The major activities have fallen into two categories: the near-term development for the experimental reactor and the long-term R&D second-generation applications, i.e., for the materials to be used in the second-stage heat exchanger installation in the experimental reactor and those for advanced-stage reactors with very high outlet temperatures. In both categories of programs, significant advances have been made, respectively, in providing and testing a modified commercial alloy with enhanced compatibility with the service environments and in selecting potential high performance alloys from the new developmental candidate alloys. Modification of the existing commercial alloy was achieved through the application of the finding on enhanced oxidation resistance by controlling the common impurities in the material, while the enhanced creep rupture strength recognized in the best performing new alloys has been attributed to the precipitation of a tungsten-rich phase (α2) during holding at test temperatures. The new alloy development program currently under way is also introduced.