Preliminary results of the loss-of-coolant heat transfer study for N- Reactor

Driver fuel cladding, process tube and graphite temperatures were experimentally simulated with an electrically heated test assembly to establish the rate of radiation heat transfer from the fuel to the process tube foilowing a loss-of-coolant incident in the N-Reactor. This information is necessary as supporting data and verification for the analytical description of such an incident. The available results of the first three of a total of six experiments are presented. These results are suitable to allow DUN to evaluate, modify, and calibrate the MELT Code which is used to analytically describe the loss-of- coolant incident in N-Reactor. (auth)