• Membrane Journal
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• v.19 no.4
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• pp.285-290
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• 2009

The permeation experiments were carried out for the nominal pore size $0.1\;{\mu}m$ and 5 mm inner diameter microfiltration tubular membrane equipped with self-designed discharging rod in order to determine the effect of fouling reduction. Dioctyl tinoxide (DOTO) latex particle was used to prepare up to 0.5 wt% concentration of feed solution, and the experiments were operated within 1.6 bar. The permeation flux effect on the discharged rod was measured as a result of flux comparison between the cases of equipped and non-equipped discharge rod modules for every experiment. The permeation flux for the case using the discharged rod was enhanced to 20% at 1.6 bar operating pressure. The improvement on permeation flux for using the discharged rod was greater as the concentration of feed increased, and reached up to 43% under 0.5 wt% concentration of feed solution.

• Nuclear Engineering and Technology
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• v.29 no.2
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• pp.175-180
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• 1997

It has been known that eater-side corrosion of fuel rods in nuclear reactor is accompanied with the metallic loss of wall thickness and hydrogen pickup in the fuel dadding tube. The fuel dad corrosion is one of the major factors to be controlled to maintain the fuel integrity during reactor operation. An oxide later thickness measuring device equipped with ECT probe system was developed by KAERI, and whose performance test was carried out in NDT(Non-destructive Test) hot-cell or PIE(Post Irradiation Examination) Facility. At first, the calibration/performance test was executed for the unirradiated standard specimen rod fabricated with several kinds of plastic thin films whose thickness ore predetermined, and the result of which showed a good precision within 10% of discrepancy. And then, hot test us peformed for the irradiated fuel rod selectively extracted from J44 fuel assembly discharged from Kori Unit-2. The data obtained with this device were compared with the metallographic result obtained from destructive examination in PIEF hot-cell on the same fuel rod to verify the validity of the measurement data.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.680-686
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• 1995

It has been known that water-side corrosion of fuel rods in nuclear reactor is accompanied with the loss of metallic wall thickness and pickup of hydrogen. This corrosion is one of the important limiting factors ill the operating life of fuel rods. In connection with the fuel cladding corrosion, a device to measure the water-side oxide layer thickness by means of the eddy-current method without destructing the fuel rod was developed by KAERI. The device was installed on the multi-function testing bench in the nondestructive test hot-cell and its calibration was carried out successfully for the standard rod attached with plastic thin films whose thicknesses are predetermined. It shows good precision within about 10% error. And a PWR fuel rod, one of the J-44 assembly discharged from Kori nuclear power plant Unit-2, has been selected for oxide layer thickness measurements. With the result of data analysis, it appeared that the oxide layer thicknesses of Zircaloy cladding vary with the length of the fuel rod, and their thicknesses were compared with those of the destructive test results to confirm the real thicknesses.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.05a
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• pp.308.2-308.2
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.945-946
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• 2004