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Nuclear Installations Safety
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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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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.
V. A. Kazakov, A. S. Pokrovsky, A. V. Smirnov
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 392-406
Technical Paper | Nuclear Fuel Cycle Education Module / Material | doi.org/10.13182/NT81-A32648
Articles are hosted by Taylor and Francis Online.
The effect of neutron irradiation on the mechanical properties, structure, and peculiarities of void formation in the Mo-Zr-B alloy within the temperature range from 400 to 1080° C and fluences (1.3 to 11.5) · 1025 n/m2 (>0.1 MeV) has been investigated. The results from radiation studies of poly- and monocrystalline molybdenum, Mo—0.12 Zr—0.16 Ti alloy and of the Mo-Zr-B alloys with different initial thermal treatment have been analyzed. At temperatures of 950 and 1080°C, the voids of nonequiaxial shape are formed, and at 1010°C only planar defects, supposedly thin precipitates, are observed. These results show a minimum swelling of the Mo-Zr-B alloy at 1010°C. It is expected that the peculiarities of void evolution in the Mo-Zr-B alloy are due to the impurity precipitation on void faces. A good correlation of the calculated and experimental values for radiation strengthening of the alloy as a result of voids and dislocation loops within a wide range of their sizes and concentrations was observed. A connection was found between the reduction of the uniform elongation within the temperature range from 400 to 900° C and voidage parameters. A maximum strengthening of the alloy takes place after irradiation at 635°C, which results from a high density of both 1.5-nm-diam voids and the dislocation loops.