System and procedure for inspection of the surface of a nuclear fuel rod for the automatic detection, location and characterization of defects
US-2024404719-A1 · Dec 5, 2024 · US
US9733074B2 · US · B2
| Field | Value |
|---|---|
| Publication number | US-9733074-B2 |
| Application number | US-201414452300-A |
| Country | US |
| Kind code | B2 |
| Filing date | Aug 5, 2014 |
| Priority date | Aug 7, 2013 |
| Publication date | Aug 15, 2017 |
| Grant date | Aug 15, 2017 |
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A method for analysing at least one fuel rod comprising a stack of nuclear fuel, a rod comprising packed zones completely filled with fuel and intermediate zones partially full of fuel, comprises: acquiring a count profile associated with a non-migrating isotope, a profile being made up of spectrometry measurements taken along the rod for this isotope; determining a set of at least one indicator K_i that makes it possible to quantify the reduction in material at an intermediate zone of index i, the said indicator being deduced from the count profile; detecting the change in geometry by comparing the set of at least one indicator K_i against a set of at least one reference value RK indicative of the initial geometry of the nuclear fuel stack.
Opening claim text (preview).
The invention claimed is: 1. A method for analyzing at least one fuel rod comprising a stack of nuclear fuel, a rod comprising packed zones completely filled with fuel and intermediate zones partially full of fuel, the method being implemented by an analysis system comprising a gamma ray spectrometry device having a sensor and a spectrometry processing unit, the method comprising the following steps: measuring gamma ray radiation emitted by the nuclear fuel with the sensor of the gamma ray spectrometry device to acquire spectrometry measurements of said at least one fuel rod; acquiring a count profile with the spectrometry processing unit associated with a non-migrating isotope in said at least one fuel rod, a count profile being derived from the spectrometry measurements taken along the at least one rod for said non-migrating isotope with the sensor of the gamma ray spectrometry device; determining with the spectrometry processing unit a set of at least one indicator K_i to quantify a reduction in material at an intermediate zone of index i, the said indicator being deduced from the count profile; and detecting a change in geometry of said at least one fuel rod with the spectrometry processing unit by comparing the set of at least one indicator K_i against a set of at least one reference value RK indicative of the initial geometry of the nuclear fuel stack. 2. The analysis method according to claim 1 , comprising a step of estimating the location of the intermediate zones by analyzing the count profile with the spectrometry processing unit. 3. The analysis method according to claim 1 , in which the detecting the change in geometry is detected in at least one intermediate zone and deduced by statistical analysis of the indicators of K_i, a change in geometry being flagged when at least one value K_i is incompatible with a theoretical measurement spread that could be expected with no change in geometry. 4. The analysis method according to claim 1 , in which the detecting the change in geometry is detected for at least one intermediate zone by comparing K_i with a predefined reference value RK, a change in geometry being detected when the ratio between K_i and RK exceeds a previously-chosen comparison threshold k1 or lies below another previously chosen comparison threshold k2. 5. The method according to claim 4 , in which the reference value RK is determined statistically by the mean of the K_i values observed experimentally over a plurality of rods of the same type. 6. The method according to claim 4 , in which the reference value RK is determined by theoretical calculation for a given pellet geometry. 7. The method according to claim 1 , in which the rod is a rod or a section of rod of PWR type made up of a plurality of pellets, an intermediate zone corresponding to an inter-pellet zone. 8. The method according to claim 1 , in which a non-migrating isotope of Ru-136 type is used to determine the count profile. 9. A system for analyzing at least one nuclear fuel rod comprising the gamma-ray spectrometry device and the spectrometry processing unit implementing the method according to claim 1 . 10. A computer program stored on a non-transitory computer readable storage medium containing instructions for executing the method according to claim 1 when the program is executed by a processor of the analysis system.
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