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A method for rapidly analyzing the 7 spectrum obtained with Ge(Li) detectors was developea for a medium-size electronic computer. The analysis is based on the first derivative method, associated with a number of peak-shape tests. The effects of data smoothing and of changes in peak width were studied to determine the optimum conditions for spectrum analysis. The resulting computer program was subjected to various quality tests on the predicted values of the peak position and area. The results of the tests showed that the code thus developed works quite satisfactorily. The code requires 10 sec and a memory core of 29 k when using a FACOM 230-60 for the analysis of a 2,047 channel spectrum.

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T h e spent fuels from the JPDR-I reactor were measured by means of a 7-scanning facility installed in t h e fuel storage pool.T h e spatial distributions of the fission products (larCs and lSiCs) were measured and analyzed in reference t o the effects of control rod pcttern. T h e ratios holding between t h e products of neutron capture and of direct fission (1a4Cs/13iCs and 16rE~/1S7Cs) were also examined for i t s relevance t o non-destructive burnup determination. T h e activity ratios of the fission products can be expressed by a linear function of burnup, provided that corrections a r e made t o account f o r differences in irradiation history and for spatial variations in t h e neutron spectrum.

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