• 멤브레인
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• 제19권4호
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• pp.285-290
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• 2009

공칭 세공크기 $0.1\;{\mu}m$이고 내경이 5 mm인 정밀여과용 관형 분리막 내에 자체 설계한 배출봉을 삽입하여 막오염 감소효과에 따른 투과유속을 측정하였다. 원료용액으로는 에멀젼 상태의 dioctyl tinoxide (DOTO) 입자를 사용하였으며 0.5 wt%까지 농도를 변화시키면서 1.6 bar 이내에서 운전하였다. 배출봉의 효과는 매 실험마다 배출봉을 삽입한 경우와 사용하지 않은 경우의 투과유속을 비교하여 평가하였다. 배출봉을 사용할 경우 운전압력 1.6 bar에서 최대 20%의 투과유속이 향상되었다. 또한 DOTO 농도가 증가함에 따라서 배출봉에 의한 투과유속 향상효과는 크게 나타났으며 0.5 wt% 농도에서 43%까지 투과유속이 향상되었다.

• Nuclear Engineering and Technology
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• 제29권2호
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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.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(2)
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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.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 요약집 춘계학술발표대회
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• pp.308.2-308.2
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.945-946
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• 2004