| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1741057 | Progress in Nuclear Energy | 2011 | 10 Pages |
Gamma-ray spectroscopy is an important nondestructive method for the qualification of irradiated nuclear fuels. Regarding research reactors, the main parameter required in the scope of such qualification is the average burnup of spent fuel elements. This work describes the measurement, using nondestructive gamma-ray spectroscopy, of the average burnup attained by Material Testing Reactor (MTR) fuel elements irradiated in the RP-10 research reactor. Measurements were performed at the reactor storage pool area using 137Cs as the only burnup monitor, even for spent fuel elements with cooling times much shorter than two years. The experimental apparatus was previously calibrated in efficiency to obtain absolute average burnup values, which were compared against corresponding ones furnished by reactor physics calculations. The mean deviation between both values amounts to 6%.
► Gamma-ray spectroscopy was employed to measure burnup attained by MTR fuel elements. ► Measurements were performed at the storage pool area of the RP-10 research reactor. ► 137Cs was burnup monitor for fuel elements with cooling times shorter than two years. ► Apparatus was calibrated in efficiency to obtain absolute average burnup values. ► The mean deviation between theoretical and measured burnup values amounts to 6%.
