NONDESTRUCTIVE ANALYSES OF IRRADIATED MITR FUEL BY GAMMA-RAY SPECTROSCOPY.
Interim scientific rept.,
MASSACHUSETTS INST OF TECH CAMBRIDGE
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Lithium drifted Ge solid state gamma ray detectors were developed and applied to the problem of nondestructive analysis of spent reactor fuel. The energy resolution of the detector was better than 1 FWHM in the 600 to 800 keV range and made possible the identification of gamma rays from Co-134, Cs-137, Rh-106, Nb-95, and Zr-95 in this energy region. Ratios of intensities of these gamma rays were used to determine average flux and irradiation time of the fuel. The burnup was then calculated. Results of these measurements agreed with other independent measurements well within the 10 error assigned. The technique developed provides a useful method for determining the irradiation history of spent reactor fuel that has been operated at low enough temperatures so that fission product migration has not taken place. Author
- Nuclear Instrumentation
- Fission Reactor Materials