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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.
Bernd A. Thiele, Hermann Diehl, Wilhelm Ohly, Heinz Weber
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 597-606
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33481
Articles are hosted by Taylor and Francis Online.
Control rods in a pebble-bed-type high-temperature reactor operate at temperatures below 650°C, but in upset conditions short-term excursions up to 850°C can occur. Here, austenitic steels or nickel-base alloys show ductility losses caused by “helium high-temperature embrittlement.” The first of a series of irradiation experiments, followed by postirradiation tensile testing, quantified the losses in ductility of eight alloys (austenitic steels and high-temperature iron- and nickel-base alloys). Relative to the initial values of the rupture elongation, the ductility losses between 600 and 850°C were the same for all alloys with the exception of the strongly precipitation-hardened alloys, which showed more severe embrittlement at 600 to 700°C. The objective of the second experiment was to optimize the microstructure of austenitic steels (1.4981 and 1.4970) by specific thermomechanical treatments to increase the ductility after irradiation. Here again, it was found that all varieties showed nearly the same relative embrittlement behavior. Thus, it can be concluded that maximum ductility after irradiation requires a material with high ductility before irradiation.