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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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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.
A. Jerry Scott, Daniel E. Wessol, Jerry L. Judd
Fusion Science and Technology | Volume 3 | Number 1 | January 1983 | Pages 129-136
Technical Paper | Blanket Engineering | doi.org/10.13182/FST83-A20823
Articles are hosted by Taylor and Francis Online.
The neutronic feasibility of testing fusing firstwall/blanket systems in a fission reactor is investigated. Heating rates resulting from a 14-MeV fusion source are calculated with one-dimensional transport theory for two tokamak blanket designs and compared with heating rates computed for the same blankets in the Engineering Test Reactor (ETR). The designs studied are a gas-cooled, liquid-lithium blanket with no neutron multiplier and a water-cooled, solid lithium-aluminate blanket with a beryllium multiplier. Based on these preliminary results, it is concluded that bulk heating rate profiles expected in tokamak reactor blankets can be simulated quite well in large (65- × 76- × 91-cm) blanket experiment modules placed on one side of the ETR core. Heating rates corresponding to tokamak wall loadings of 1 MW/m2 can be achieved, and the level varied to simulate the cyclic operation typical of tokamaks.