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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.
Om Prakash Joneja, Vijay R. Nargundkar
Fusion Science and Technology | Volume 8 | Number 3 | November 1985 | Pages 2721-2726
Technical Note | Blanket Engineering | doi.org/10.13182/FST85-A24693
Articles are hosted by Taylor and Francis Online.
The multilayered blanket concept introduced initially in spherical geometry has been extended to tokamak geometry, which has been approximated by an annular disk geometry for the present calculations. Tritium production is determined, using such commonly available materials as lead, natural lithium, and graphite/water. The Morse-E general geometry package is employed to simulate the blanket geometry and the plasma region where the neutrons are produced. Calculations are performed for both the block- and the multilayered-type blanket configurations. Using water as a moderator/reflector, the multilayered arrangement gives a 75% higher tritium production compared to the block-type blanket with the same overall size of assembly. The advantage in tritium breeding due to the multilayered arrangement remains practically the same when 10 vol% stainless steel structural material is used; however, the absolute value of tritium breeding decreases by 6 to 8%. Calculations are reported for a homogeneous, block, and multilayered arrangement of materials. Using lead, natural lithium, and water in the annular disk geometry, an overall thickness of 35 cm would be sufficient to give tritium breeding of 1.32/source neutron.