Apparatus for determining the local power generation rate in a nuclear reactor fuel assembly
AssigneeScandpower A/S
InventorsErik Rolstad, Thor-Harrald Korpas, Robert H. Leyse, Robert D. Smith
Life of this patent
Estimating the term…
Loading patent…
AssigneeScandpower A/S
InventorsErik Rolstad, Thor-Harrald Korpas, Robert H. Leyse, Robert D. Smith
Estimating the term…
There is disclosed an elongated cylindrical rod of heat-conducting and electrically-conducting material having a central bore containing a plurality of thermocouples, the hot and cold junctions of which are placed respectively in separate zones along the rod. In each zone, the hot junction of one thermocouple is fixed generally in position axially at the midway of an annular reduced-section portion of the cylindrical rod, the cold junction is located generally axially between two reduced-diameter portions and an annular insulating chamber is defined annularly opposite to each reduced-diameter portion by an outer shielding tube. The outer tube surrounds the cylindrical rod. The completed unit is to be placed within a reactor core fuel assembly to be monitored.
A device for measuring local power generation rate within neighboring fuel pins of a nuclear reactor core fuel assembly by generating signals from gamma heating which can be calibrated by direct electrical resistance heating over the entire range of in-reactor gamma heat rates, said device comprising:
A device for measuring local power generation rate within a nuclear reactor fuel assembly comprising:
A device for measuring local power generation rate within a nuclear reactor fuel assembly comprising:
Dependencies are inferred from the claim text.