Experimental Determination of Thermal Conductivity of a Lead- Bismuth, Eutectic-Filled Annulus

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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Bibliographic Details
Main Authors: Carpenter, David M., Kohse, Gordon E.
Other Authors: Massachusetts Institute of Technology. Nuclear Fuel Cycle Program
Format: Technical Report
Published: Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Fuel Cycle Program 2012
Online Access:http://hdl.handle.net/1721.1/75212

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