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TRIAC Progress Report - KEK

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container of ion source and uranyl nitrate ( nat UO2(NO3)2 / 3M HNO3) solution was<br />

impregnated. After drying in air atmosphere for the formation of UO2(NO3)2-6H2O, the<br />

nitrates were out-gassed and converted to oxides such as U3O8 at about 900 K for about<br />

1.5 hours in argon atmosphere. Then the target container of the oxides is loaded in the<br />

target-ion source system, where the oxides are converted into UCx by in-situ sintering at<br />

about 1800 K for about a half day. The target container (9 mm in diameter and 11-mm<br />

long in case of FEBIAD-B2) is heated by electron bombardment (EB-heating). The<br />

electrons were generated from the filament of the target heater. The potential difference<br />

between the filament and the target container is about 200 V. A certain variation of the<br />

target temperature does not affect the discharge parameters since the target chamber is<br />

equipotential with the anode. The electric power of about 120 W (160 V / 0.75 A) was<br />

supplied for the anode, about 180 W (220 V / 0.8 A) for EB-heating the target container,<br />

when operating at the temperature of 1850 ± 50 K and 1800 ± 50 K, respectively. The<br />

temperatures at the anode and the target were measured with an optical pyrometer and<br />

the corresponding input powers were calibrated with the temperatures. Along this way,<br />

in-situ preparation of UCx target was performed and the typical thickness of the carbide<br />

target corresponds to the thickness of 600-800 mg/cm 2 of nat U. The process for target<br />

preparation is summarized in Fig. 2-3.<br />

Fig. 2-3. Target processing and photograph of the target base material.<br />

The target/ion source was operated at temperature of about 1800 K and at the<br />

pressure approximately 2 x10 -4 Pa. During the operation, ionization efficiencies for<br />

stable xenon and krypton isotopes were periodically checked by using calibrated leaks<br />

of 2.3 x 10 -7 and 4.6 x10 -7 atm cm 3 /s, respectively. The separation yields and<br />

efficiencies for typical uranium fission fragments were summarized in Table 2-2. The<br />

separation efficiency for an isotope is defined as the ratio of the yield mass-separated to<br />

the calculated yield of production.<br />

Although high separation efficiency was observed in the FEBIAD-B2 type ion<br />

source, short-lived isotopes with half-lives shorter than 0.5 s such as 130, 131 In were<br />

5

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