Devitrifikasi Gelas Limbah Dan Korosi Canister Dalam Storage Dan Disposal Limbah Radioaktif

WASTE GLASS DEVITRIFICATION AND CANISTERS CORROSION IN RADIOACTIVE WASTE STORAGE AND IN DISPOSAL. High level liquid waste arising from the reprocessing of spent fuel contains of many fission products and a few actinides. This waste is vitrified with borosilicate glass to become waste-glass form which is poured into canisters at a temperature of
1150 0C. The canisters are temporarily stored in storage and finally disposed in geological formations. Devitrification of waste glass and canister corrosion possibly occurs in the storage due to either decay heat from the fission products or the heat of waste glass melt that can not be
accommodated by the process cooling system during pouring of the melt into glass canisters. While the possibility of contact between the canister with water intruding into the disposal might increase the rate of canister corrosion and leaching rate of the waste glass. A simulation on devitrification of waste glass containing waste of 20 % and 30 % by weight which was heated at the range of
(600∼1100 0C) for 1∼30 hours. While the canister corrossion study was performed by heating
stainless steel samples of AISI 304 , 304L and 321 are heated at a temperature of 700 and 1100 0C
for 2 hours. The results showed that the waste glass containing waste of 30 % was easier to devitrify than the waste glass containing 20 % by weight. The leaching rate of the devitrified waste glass was higher significantly than the leaching rate of a standard waste glass. The corrosion rate of materials AISI 304, 304L and 321 which were heated at a temperature of 700 0C was greater than that of materials heated at 1100 0C. The magnitude of the corrosion rate was in the order of AISI 304 > AISI 304L > AISI 321, eiter in the medium of sea water or in bentonite solution.

Keywords: high level liquid waste, waste glass, devitrification, canister, corrosion