[en] Under the CORA experimental program conducted at the Karlsruhe Nuclear Research Center (KfK) the fuel element behavior is being investigated at temperatures up to and beyond 2000 C. These temperatures are attained by electric heating of some fuel pins from the bundle. The CORA experiments were performed under the Nuclear Safety Research Project (PSF). The experiments are part of the KfK research program on the experimental investigation of severe core damage in light water reactors (LWR). The CORA experiments are being evaluated both on the basis of the values measured and video tapes recorded during the experiment and, in addition, in extensive destructive post-test examinations of material specimens collected from the overheated fuel pin bundle. In this report the analytical results are presented of investigations performed in the microrange with the scanning electron microscope (SEM) and the connected energy dispersive X-ray spectrometer (EDX) on four transverse microsections and one longitudinal microsection of the CORA-16 fuel pin bundle. The CORA-16 experiment was performed with the objective to obtain information on the damage mechanisms which may get active in the excessively heated core of a boiling water reactor (BWR) until the onset of non-controlled melting. The experimental data derived form the basis for the comparison with results of computations using code systems, which describe analytically the destruction of the bundle. This is the reason why the fuel pin bundle was subjected to an intensive metallographic and chemical-analytical post-test examination. (orig.)