Apparatus for determining the local power generation rate in a nuclear reactor fuel assembly

Patent · Tue Nov 03 04:00:00 EST 1981

OSTI ID:5513838

Korpas, T; Leyse, R H; Rolstad, E; Smith, R D

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.

• Assignee: Scandpower A/s (Norway)
• Patent Number(s): US 4298430
• OSTI ID: 5513838
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ANNULAR SPACE
CONFIGURATION
ELECTROMAGNETIC RADIATION
FUEL ASSEMBLIES
FUELS
GAMMA RADIATION
IONIZING RADIATIONS
JUNCTIONS
MEASURING INSTRUMENTS
MONITORING
POWER GENERATION
RADIATIONS
REACTOR COMPONENTS
REACTOR CORES
SHIELDS
SPACE
THERMOCOUPLES
THERMOMETERS
ZONES