Experimental Determination of Thermal Conductivity of a Lead- Bismuth, Eutectic-Filled Annulus
In order to obtain an accurate prediction of the thermal behavior of an annular fuel assembly (see MIT-NFC-PR-048 for a description of the rods), the thermal conduction of the region from the outside of the fuel capsule to the reactor coolant (within the test assembly) must be known. The effectiv...
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Format: | Technical Report |
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Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program
2012
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Online Access: | http://hdl.handle.net/1721.1/75212 |