The "In-pile tritium-release experimental apparatus" was designed and installed at JRR-4 in order to study tritium release from UO
2 during reactor operation. It mainly consists of three systems: the irradiation rig, the gas-supplying system and the tritium-collecting system. The mixture of Ne and H
2 was used as a sweep gas to avoid the tritium-contamination by the nuclear reaction of the sweep gas and the adsorption of the released tritium on the surface of the irradiation rig. The released tritium was transformed to HT by the isotopic exchange reaction HTO+H
2=HT+H
2O, and collected into the water-bubbler after oxidizing to tritiated water by CuO. The temperature of UO
2 irradiated was controlled by changing either the ratio of H
2/Ne mixture gas or the distance between the irradiation rig and reactor core surface. The experimental temperature was from about 400 to 1, 000°C.
抄録全体を表示