Measuring apparatus for the coolant outlet temperature in nuclear-reactor fuel elements

摘要

A measuring apparatus for the coolant outlet temperature in nuclear reactor fuel elements particularly gas cooled fast breeder reactors is disclosed. The apparatus comprises a fuel element adapted to permit internal flow of coolant over the individual fuel elements with a variable choke adapted to regulate coolant flow rate. The temperature of the coolant after it passes over the fuel rods is measured by a temperature sensor which is removably mounted in an internal guide tube which passes through the fuel element and its supporting structure.