• Nuclear Engineering and Technology
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• v.52 no.3
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• pp.581-588
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• 2020

The membrane fouling is an important problem for FO applied to the radioactive wastewater treatment. The FO fouling characteristics for simulated radioactive wastewater treatment was investigated. On-line cleaning by deionized (DI) water and external cleaning by ultrasound and HCl were applied for the fouled membrane. The effectiveness and foulant removing amount by each-step cleaning were evaluated. The membrane fouling was divided into three stages. Co(II), Sr(II), Cs(I), Na(I) were all found deposited on both active and support layers of the membrane surface, resulting in membrane surface became rougher and more hydrophobic, which increased membrane resistance. On-line cleaning by DI water recovered the water flux to 69%. HCl removed more foulants than ultrasound.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.02a
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• pp.12-27
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• 2004

Pretreatment process consisted of submerged hollow-fiber microfiltration(HMF) membrane and spiral-wound nanofiltration(SNF) membrane has been developed by NETEC, KHNP for the purpose of improving the impurities of liquid radioactive waste before entering Selective Ion Exchange System(SIES). The lab-scale combined system was installed at Kori NPP #2 nuclear power plant and demonstration tests using actual liquid radioactive waste were carried out to verify the performance of the combined system. The submerged HMF membrane was adopted for removal of suspended solid in liquid radioactive waste and the SNF membrane was used for removal of particulate radioisotope such as, Ag-l10m and oily waste because ion exchange resin can not remove particulate radioisotopes. The liquid waste in Waste Holdup Tank (WHT) was processed with HMF and SNF membrane, and SIES. The initial SS concentration and total activity of actual waste were 38,000ppb and $1.534{\times}10_{-3}{\mu}Ci/cc$, respectively. The SS concentration and total activity of permeate were 30ppb and lower than LLD(Lower Limit of Detection), respectively.

• Proceedings of the Membrane Society of Korea Conference
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• 2003.11a
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• pp.25-33
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• 2003

It summarized about the application of the membrane technology in thermochemical water-splitting iodine-sulfur process that was hydrogen production using the nuclear heat from the High Temperature Gas-Cooled Reactor (HTGR). Thermochemical water-splitting hydrogen production method using the high temperater nuclear thermal energy could be realized and remained to be solved the investigation subject. And, it is possible for mass-production of hydrogen such as one of the clean energy in future.

• Membrane and Water Treatment
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• v.3 no.4
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• pp.231-242
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• 2012

The performance of a nanofiltration membrane for treatment of a low-level radioactive liquid waste was investigated through static and dynamic tests. The liquid waste ("carbonated water") was obtained during conversion of $UF_6$ to $UO_2$. In the static tests membrane samples were immersed in the waste for 24, 48 or 72 h. The transport properties of the samples (hydraulic permeability, permeate flow, selectivity) were evaluated before and after immersion in the waste. In the dynamic tests the waste was permeated in a permeation flow front system under 0.5 MPa, to determine the selectivity of NF membranes to uranium. The surface layer of the membrane was characterized by zeta potential, field emission microscopy, atomic force spectroscopy and infrared spectroscopy. The static test showed that the pore size distribution of the selective layer was altered, but the membrane surface charge was not significantly changed. 99% of uranium was rejected after the dynamic tests.

• Applied Microscopy
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• v.5 no.1
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• pp.21-30
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• 1975

To investigate ultrastructural characteristics of cancer cell nucleus, 29 cases of malignant tumors of 9 different types were examined. The common findings were marked irregularity of nuclear membrane with pronounced infoldings, clumping of heterochromatin along inner nuclear membrane, enlargement and disturbance of configuration and composition of nucleolus, and frequent observations of nuclear bodies and nuclear inclusions. These findings confirm what have been observed by light microscopy, and are also the signes that can be observed in hyperactive cells. Thus, ultrastructural characteristics of cancerous nucleus are the great variability of nuclear size, shape and composition, but none of them appear to be specific.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.427-432
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• 1998

중수속의 삼중수소 제거 공정인 액상 촉매 교환 반응에서 중수의 촉매 표면 응축에 의한 성능 저하가 큰 문제의 하나로서 성능 저하를 감소시키기 위한 여러 가지 형태의 촉매탑이 고안 되었다. 본 연구에서는 membrane을 사용하여 중수와 촉매를 분리시킴으로써 촉매 성능 저하를 감소시킬 수 있는 촉매탑의 설계를 시도하였다. 세 가지 촉매탑이 고안되었는데 sheet type의 membrane을 사용한 multilayered type 과 double spiral type, hollow fiber membrane을 사용한 hollow fiber cartridge type 등이다. multilayered type은 구조가 단순하여 scale-up이 용이하고 double spiral type은 다른 type보다 유로의 blocking 문제가 작고 hollow fiber cartridge type은 최대의 비표면적을 가질 수 있다.

• Transactions of the Korean hydrogen and new energy society
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• v.29 no.2
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• pp.226-234
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• 2018

Even though the nuclear power plants has many advantages, safety issues of nuclear power plants are crucial factors of reliable operation. A tritium detector is a useful sensor to analyze amount of exposed radiation from the nuclear power plants. Currently, concentration of underwater tritium is measured precisely but it takes very long time. Since electrolysis is extracted hydrogen from the coolant of nuclear power plant, it can motivate to develop new type of real-time sensor. In this study, Proton Exchange Membrane (PEM) electrolyzer is studied for candidate as preprocessor of real-time tritium detector. Characteristics of the unit PEM electrolyzer were experimentally investigated. A simulation model is developed to understand physical behavior of unit PEM electrolyzer under dynamic operation.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.10a
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• pp.181-182
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• 2005

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.323-324
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• 2005

• Membrane Journal
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• v.14 no.3
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• pp.185-191
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• 2004

It summarized about the properties of thermochemical water-splitting iodine-sulfur process that was hydrogen production using the waste heat from the High Temperature Gas-Cooled Reactor (HTGR) recycling the heat of nuclear power. It was mainly explained about the application of membrane separation technique in IS process. Thermochemical water-splitting hydrogen production method using the high temperature nuclear thermal energy could be realized and remained to be solved the investigation subject. And, it is possible for mass-production of hydrogen such as one of the clean energy in future.