Possibilities for the Determination of the Heat Transfer Process Between Nuclear Fuel Rods and the Cooling Medium in a Sodium-Cooled Reactor During Operation

摘要

In order to improve the safety, the surveillance and economy of sodium cooled reactors it is desirable to obtain a more precise knowledge of the heat transfer between the fuel and the coolant. Different possibilities have been investigated to determine the corresponding heat transfer coefficient by measuring the pertinent transfer functions. The result was the following: the heat transfer coefficient can be determined with reasonable accuracy at the KNK II and the SNR by means of small pseudo-stochastic power oscillations. These power oscillations must be artificially induced but do not require an interruption of the normal plant operation. (ERA citation 05:020630)