FREMGANGSM}TE OG APPARAT FOR } BESTEMME DEN RADIALE AVSTAND MELLOM BRENSEL OG DEN OMGIVENDE KAPSLING I EN BRENSELSSTAV FOR KJERNEREAKTORER.

摘要

A fuel rod for nuclear reactors normally comprises an internal fuel core surrounded by an external cladding, a radial spacing being advantageously arranged between said core and cladding in order to avoid hard interaction between said parts. According to the present invention said spacing is gauged by elastically squeezing the cladding at least until contact with the internal fuel core is obtained. During the squeezing process the change of elastic behavior of the squeezed cladding at the instance of said contact formation is detected by repeatedly or continuously sensing the applied squeezing force and resulting cladding deformation, the elastic deformation at said instance being measured as an expression of the spacing to be gauged.