UJI INTEGRITAS KELONGSONG BAHAN BAKAR NUKLIR BEKAS REAKTOR DENGAN METODE UJI CICIP

ABSTRACT
INTEGRITY TEST OF THE SPENT NUCLEAR FUEL USING SIPPING TEST METHOD. The integrity of the spent nuclear fuel have been tested to determine the leakage of spent nuclear fuel cladding with a batch number RI-309, RI-358, RI-389. Batch Number Selection is based loading and unloading from reactor core and burn up. Sipping test is one of the non-destructive testing techniques for detection the leakage of spent fuel cladding by detecting and identifying the presence of fission radionuclides, the existence of Cs 137 in the water after irradiated as an indicator of a leakage. The integrity test on 3 of spent fuel have been done with radionuclide identification and activity measurements using gamma spectrometry. The results of the immerse of spent fuel for 4, 22, 46 and 142 hours and concentrations measurements using gamma spectrometry. The result is a fuel with a batch number RI-309 in 142 hours immersion concentration of Co-60 = 2.0 x 10 -6 µCi / ml , RI-375 in 142 hours immersion concentration Co 60 = 5,40 x 10-6 µCi / ml and 142 hour immersion concentration of Co-60 = 5.4 x 10 -6 µCi / ml; and RI-389 in 142 hours immersion concentration of Co-60 = 3,0 x 10 -6 µCi / ml. From these results indicate that there are no leaks in the spent fuel is detected. The presence of Cs137 in the water immersion for further analysis to know the source and cause of radionuclide released. While the presence of Co60 indicates the result of activation product from reactore core in cladding material, although still within the allowable threshold.

Keywords: leakage of spent nuclear fuel, fission product, sipping test, γ-ray spectrometry