Fuel rod internal pressure measurement
View Patent ↗A method for determining a leaking nuclear fuel rod that remotely measures the internal pressure in the plenum region of the fuel rod by remotely measuring the thermal response of the rod when a localized heating is imposed on the outside of the rod in the plenum region. The temperature of the cladding at two symmetrically spaced points on either side of the location where the heating is imposed is remotely monitored as a function of time and compared to a standard to determine the internal pressure of the plenum.
1. A method of measuring the integrity of an elongated nuclear fuel rod having an axial dimension by a thermal response of a gas within a plenum of the fuel rod comprising the steps of:
applying heat from an outside, remote, non-contact source to a portion of a cladding surface of the fuel rod within a plenum area;
remotely monitoring a temperature of the cladding surface along the plenum at at least four spaced axial locations within the plenum area, as a function of time over a period of approximately one minute or less, the four spaced locations being divided into at least two sets of two spaced locations each;
determining the difference in temperature between the two spaced locations in each set as a function of time employing a non contact sensor; and
comparing that difference to a standard to determine the integrity of the fuel rod.
2. The method of claim 1 wherein the comparing step determines the relative pressure of the gas within the plenum.
3. The method of claim 1 wherein the two spaced axial locations in each of the two sets are on either side of the portion of the cladding surface that the heat was applied to.
4. The method of claim 3 wherein the two spaced axial locations in each set are situated symmetrically on either side of the portion of the cladding surface that the heat was applied to.
5. The method of claim 4 wherein the two spaced locations in one of the two sets are 0.38 in. (0.97 cm.) on either side of the portion of the cladding surface that the heat was applied to.
6. The method of claim 4 wherein the two spaced locations in another of the two sets are 0.82 in. (2.08 cm.) on either side of the portion of the cladding surface that the heat was applied to.
7. The method of claim 1 wherein the applying step remotely applies heat from a point source.
8. The method of claim 7 wherein the point source is a laser.
9. The method of claim 1 wherein the monitoring step is performed with an infrared system.
10. A method of determining the integrity of a nuclear fuel rod within a fuel assembly comprising the steps of:
Remotely heating a cladding surrounding a gas plenum of the fuel rod with a point heating source;
Remotely measuring a thermal response of a gas inside the fuel rod as a function of time;
comparing the thermal response over time to a standard;
determining whether the temperature of the gas decreased over time slower than the standard; and
wherein the remotely heating and remotely measuring steps are performed successively on each fuel rod in a row of the fuel assembly so as to scan the row.
11. The method of claim 10 wherein the thermal response is measured by remotely determining the temperature difference between two spaced points in each of at least two sets along an axial dimension in a plenum area of the nuclear fuel rod.
12. The method of claim 10 wherein the standard was obtained from at least one other fuel rod within the fuel assembly.
13. The method of claim 10 including the step of shielding a second row in back of the row being scanned from the point heating source.