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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.
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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
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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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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.
Shunsuke Uchida, Masao Kitamura, Yasunori Matsushima, Koichi Yonezawa, Katsumi Ohsumi, Minoru Miki
Nuclear Science and Engineering | Volume 77 | Number 4 | April 1981 | Pages 496-501
Technical Note | doi.org/10.13182/NSE81-A18963
Articles are hosted by Taylor and Francis Online.
The characterization of radioactive corrosion products deposited on the internal surfaces of recirculation pipes was carried out to determine the deposited amounts and configurations. The test specimens were taken from the auxiliary pipes of the recirculation lines of Shimane Nuclear Power Plant after operation for ∼20 000 effective full-power hours. As a result of characterizing them, it was demonstrated that 60Co, which determined the contact dose rate, was difficult to remove by mechanical washing the amount of 60Co deposited was reduced by more than a factor of 10 by oxalic acid polishing and by a factor of ∼1000 by electro-polishing both the particle size and 60Co specific activity of the deposits removed by the mechanical washing (designated as soft deposits) were the same as those of the crud suspended in the reactor water the 60Co specific activity of the deposits removed by the oxalic acid polishing (designated as hard deposits) was ten times greater than that of the suspended crud. It was inferred that the soft deposits were formed by direct deposition of the suspended crud, and the hard deposits were formed by oxidation of the stainless-steel base metal with 60Co being taken into the oxide layers.