System and method for local resistivity measurement and critical heat flux calculation for nuclear reactor cladding tubing
Disclosed are a voltage drop measurement system and methods for measuring resistivity of a nuclear reactor cladding. The system includes a short cladding sample of a nuclear reactor cladding. Two electrically conductive plugs are attached to the short cladding. A power supply is electrically coupled to the each of the two electrically conductive plugs and is configured to apply an electrical current to the short cladding through the two electrically conductive plugs. Two needle like probes are electrically coupled to a surface of the short cladding between the two electrically conductive plugs. The needle like probes are spaced apart by a distance L. Resistivity and heat flux are determined in accordance with Equations (1)-(4).
1. A system comprising:
a portion of a nuclear reactor cladding, wherein the portion of the nuclear reactor cladding has a first end and a second end, wherein the portion of the nuclear reactor cladding is physically divided into multiple segments, wherein each segment of the multiple segments extends between the first end and the second end, wherein each of the multiple segments of the portion of the nuclear reactor cladding comprises an outer surface extending between the first end and the second end;
two electrically conductive plugs, wherein a first electrically conductive plug of the two electrically conductive plugs is attached to the first end and a second electrically conductive plug of the two electrically conductive plugs is attached to the second end;
a power supply electrically coupled to each of the two electrically conductive plugs and configured to apply an electrical current to the portion of the nuclear reactor cladding through the two electrically conductive plugs;
a voltmeter; and
two needle probes electrically coupled to the outer surface of one of the segments of the multiple segments and to the voltmeter, wherein the two needle probes are spaced apart by a distance L,
wherein the voltmeter is configured to measure a voltage difference between the two needle probes to calculate a resistivity for the one of the segments of the multiple segments, wherein the needle probes are configured to be coupleable to each of the segments, wherein the voltmeter is configured to measure a voltage difference between the two needle probes to calculate a resistivity for each segment of the multiple segments using the voltage difference.
2. The system of claim 1 , comprising a thermocouple attached to an interior surface of at least one of the multiple segments of the portion of the cladding.
3. The system of claim 1 , wherein the electrical current is a constant current applied to each of the multiple segments and a voltage is measured across each of the multiple segments.
4. The system of claim 1 , comprising a thermocouple attached to an interior surface of each of the multiple segments.
5. The system of claim 1 , wherein the multiple segments comprise four segments.
6. A system comprising:
a portion of a nuclear reactor cladding, wherein the portion of the nuclear reactor cladding has a first end and a second end, wherein the portion of the nuclear reactor cladding is physically divided into four quadrants, wherein each of the quadrants extends between the first end and the second end; wherein each of the quadrants of the portion of the nuclear reactor cladding comprises an outer surface extending between the first end and the second end;
two electrically conductive plugs, wherein a first electrically conductive plug of the two electrically conductive plugs is attached to the first end and a second electrically conductive plug of the two electrically conductive plugs is attached to the second end;
a power supply electrically coupled to each of the two electrically conductive plugs and configured to apply an electrical current to the portion of the nuclear reactor cladding through the two electrically conductive plugs;
a voltmeter; and
two needle probes electrically coupled to the outer surface of one of the quadrants and to the voltmeter, wherein the two needle probes are spaced apart by a distance L,
wherein the voltmeter is configured to measure a voltage difference between the two needle probes to calculate a resistivity for each of the quadrants using the voltage difference, wherein the needle probes are configured to be coupleable to each of the quadrants.
7. The system of claim 6 , comprising a thermocouple attached to an interior surface of at least one of the quadrants of the portion of the cladding of the portion of the cladding.
8. The system of claim 6 , wherein the electrical current is a constant current applied to each of the quadrants and a voltage is measured across each of the quadrants.
9. The system of claim 6 , comprising a thermocouple attached to an interior surface of each of the quadrants.
10. A system comprising:
a portion of a nuclear reactor cladding, wherein the portion of the nuclear reactor cladding has a first end and a second end, wherein the portion of the nuclear reactor cladding is physically divided into multiple segments, wherein each segment of the multiple segments extends between the first end and the second end, wherein each of the multiple segments of the portion of the nuclear reactor cladding comprises an outer surface extending between the first end and the second end;
two electrically conductive plugs, wherein one a first electrically conductive plug of the two electrically conductive plugs is attached to the first end and a second electrically conductive plug of the two electrically conductive plugs is attached to the second end;
a power supply electrically coupled to each of the two electrically conductive plugs and configured to apply an electrical current to the portion of the nuclear reactor cladding through the two electrically conductive plugs;
a voltmeter; and
two needle probes electrically coupled to the outer surface of one of the segments of the multiple segments and the voltmeter, wherein the two needle probes are spaced apart by a distance L.
11. The system of claim 10 , wherein the electrical current is a constant current applied to each of the multiple segments and the voltmeter is configured to measure a voltage across each of the multiple segments.
12. The system of claim 10 , comprising a thermocouple attached to an interior surface of each of the multiple segments.
13. The system of claim 10 , wherein the multiple segments comprise four longitudinal segments of the portion of the nuclear reactor cladding.
14. The system of claim 10 , comprising a thermocouple attached to an interior surface of at least one of the multiple segments of the portion of the cladding.