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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.

Precise measurements of burnup and accumulated transuranium elements were carried out on specimens which were taken out from spent fuel of Japan Power Demonstration Reactor (JPDR) -I, by means of chemical analysis and r-ray spectrometry. Results of the measurements are summarized numerically. Core configuration and operational history of the reactor are also described.