• Journal of Korean Society of Environmental Engineers
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• v.38 no.12
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• pp.662-666
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• 2016

This study investigated removal of radionuclides (Cs, Sr) in surface water by coagulation and precipitation. Jar tests were conducted with various chemical and natural coagulants to remove the stabilized radionuclides ($^{133}Cs$, $^{88}Sr$). Chemical coagulants included aluminum sulfate, poly aluminum chloride, and poly aluminum hydroxide chloride silicate (PACS); natural coagulants (minerals) included illite and zeolite. Chemical coagulant alone could achieve removals of Cs and Sr less than 10%; The removals increased up to 23.1% for Cs and 17.8% for Sr with addition of poly-dimethyldiallylammonium chloride (polyDADMAC) along with the chemical coagulants. Compared with chemical coagulants, natural coagulants (minerals) could achieve higher removals of Cs and Sr. Addition of zeolite along with PACS and polyDADMAC increased the removal rates up to 36.9% for Cs and 17.1% for Sr.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.7 no.2
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• pp.73-78
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• 2009

The decay heat of Cs and Sr contained in a LiCl waste salt, generated from an electrolytic reduction process in pyroprocessing of spent nuclear fuel, has been calculated. The calculation has been carried out under some assumptions that most of the LiCl waste is purified and recycled to main process, and the residual is fabricated to make a waste form. As a result, the decay heat from daughter nuclides such as Ba and Y seems to be maximum 4.6 times higher than that from their parent nuclides such as Cs and Sr. The thermal release from Cs and Sr in the LiCl waste is the maximum around the first one month, so an cooling system operation for some time at the beginning would be suggested to control a rapid increase in the temperature of the LiCl waste salt.

• Journal of Korean Society of Environmental Engineers
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• v.37 no.3
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• pp.145-151
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• 2015

In order to remove Sr ions and Cs ions from aqueous solution, PS-zeolite beads were prepared by immobilizing zeolite with polysulfone (PS). The prepared PS-zeolite beads were characterized by SEM, XRD, FT-IR, and TGA. The optimum condition to prepare PS-zeolite beads was 1.25 g of PS content and 2 g of zeolite A. The removal efficiencies of Sr and Cs ions by the PS-zeolite beads increased as the solution pH increases and nearly reached a plateau at pH 4. The PS-zeolite beads prepared in this study showed a remarkably high selectivity for Sr ion and Cs ion under the coexistence of ions such as $Na^+$, $K^+$, $Mg^{2+}$, and $Ca^{2+}$. Zeolite particles detached from the PS-zeolite beads were not observed on this experiments, and also the PS-zeolite beads maintained the morphological structure on a SEM image. The removal efficiencies of Sr ions and Cs ions by PS-zeolite beads were maintained over 90% even after five adsorption-desorption cycles. These results implied that the prepared PS-zeolite beads could be an available adsorbent for the adsorption of Sr and Cs ions. These results suggest that the PS-zeolite can potentially be used as an adsorbent in radioactive ions removal for the treatment of industrial wastewater.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.2
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• pp.101-112
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• 2016

This study investigated the removal of Sr, which was one of the high radioactive nuclides, by adsorption with Barium (Ba) impregnated 4A zeolite (BaA) from high-radioactive seawater waste (HSW). Adsorption of Sr by BaA (BaA-Sr), in the impregnated Ba concentration of above 20.2wt%, was decreased by increasing the impregnated Ba concentration, and the impregnated Ba concentration was suitable at 20.2wt%. The BaA-Sr adsorption was added to the co-precipitation of Sr with $BaSO_4$ precipitation in the adsorption of Sr by 4A (4A-Sr) within BaA. Thus, it was possible to remove Sr more than 99% at m/V (adsorbent weight/solution volume)=5 g/L for BaA and m/V >20 g/L for 4A, respectively, in the Sr concentration of less than 0.2 mg/L (actual concentration level of Sr in HSW). It shows that BaA-Sr adsorption is better than 4A-Sr adsorption in for the removal capacity of Sr per unit gram of adsorbent, and the reduction of the secondary solid waste generation (spent adsorbent etc.). Also, BaA-Sr adsorption was more excellent removal capacity of Sr in the seawater waste than distilled water. Therefore, it seems to be effective for the direct removal of Sr from HSW. On the other hand, the adsorption of Cs by BaA (BaA-Cs) was mainly performed by 4A within BaA. Accordingly, it seems to be little effect of impregnated Ba into BaA. Meanwhile, BaA-Sr adsorption kinetics could be expressed the pseudo-second order rate equation. By increasing the initial Sr concentrations and the ratios of V/m, the adsorption rate constants ($k_2$) were decreased, but the equilibrium adsorption capacities ($q_e$) were increasing. However, with increasing the temperature of solution, $k_2$ was conversely increased, and $q_e$ was decreased. The activation energy of BaA-Sr adsorption was 38 kJ/mol. Thus, the chemical adsorption seems to be dominant rather than physical adsorption, although it is not a chemisorption with strong bonding form.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.4
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• pp.347-353
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• 2010

Source terms of metal waste comprising a spent fuel assembly are relatively important when the spent fuel is pyroprocessed, because cesium, strontium, and transuranics are not a concern any more in the aspect of source term of permanent disposal. In this study, characteristics of radiation source terms for each structural component in spent fuel assembly was analyzed by using ORIGEN-S with a assumption that 10 metric tons of uranium is pyroprocessed. At first, mass and volume for each structural component of the fuel assembly were calculated in detail. Activation cross section library was generated by using KENO-VI/ORIGEN-S module for top-end piece and bottom-end piece, because those are located at outer core with different neutron spectrum compared to that of inner core. As a result, values of radioactivity, decay heat, and hazard index were reveled to be $1.40{\times}10^{15}$ Bequerels, 236 Watts, $4.34{\times}10^9m^3$-water, respectively, at 10 years after discharge. Those values correspond to 0.7 %, 1.1 %, 0.1 %, respectively, compared to that of spent fuel. Inconel 718 grid plate was shown to be the most important component in the all aspects of radioactivity, decay heat, and hazard index although the mass occupies only 1 % of the total. It was also shown that if the Inconel 718 grid plate is managed separately, the radioactivity and hazard index of metal waste could be decreased to 20~45 % and 30~45 %, respectively. As a whole, decay heat of metal waste was shown to be negligible in the aspect of disposal system design, while the radioactivity and hazard index are important.

• Journal of the Mineralogical Society of Korea
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• v.27 no.1
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• pp.41-51
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• 2014

The four natural zeolites collected in Pohang and Gyeongju area, Kyungsangbuk-do, Korea, were characterized by XRD, XRF, DTA, TGA, and CEC analysis. The primary species of these zeolite are heulandite, modenite, illite, and illite in Kuryongpo (Ku), Pohang (Po), Yangbuk-A (Ya-A), and Yangbuk-B (Ya-B) samples. The XRF analysis showed that the four zeolites contain Si, Al, Na, K, Mg, Ca, and Fe. Cation exchange capacity of Kuryongpo (Ku) zeolite was the highest compared to other zeolites. The adsorption capacities of Cs and Sr in the four natural zeolites were compared at $25^{\circ}C$. On the basis of adsorption data Langmuir and Freundlich adsorption isotherm model were confirmed. The equilibrium process was descried well by Langmuir isotherm model. This study shows that Ya-A zeolite is the most efficient for the $Cs^+$ and $Sr^{2+}$ ion adsorption compared to the other natural zeolites.

• Proceedings of the Korea Water Resources Association Conference
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• 2007.05a
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• pp.805-809
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• 2007

최근 도시의 발달은 하상공간에 대한 이용도를 높이는 방향으로 개발이 진행되어가는 추세이며, 하상도로 및 하상주차장의 이용은 이제 도시 내에서 이용 가능한 마지막 여유 공간으로 인식될 정도로 그 의존도가 높아져가고 있다. 그러나 하상공간의 활용도가 높아져갈수록 도시홍수의 발생으로 인한 대피문제가 발생하게 되고 돌발홍수로 인하여 하상도로의 차단 혹은 하상 주차장에 주차된 차량의 소거가 늦어지는 경우 고스란히 피해를 보게 되는 등 그 부작용도 계속 증가되고 있다. 도시홍수의 특성을 살펴보면 국지성 돌발 강우에 의한 유량의 급격한 증가와 짧은 유하시간, 작은 유역면적 등에 의하여 주요 예보지점까지의 도달시간이 매우 짧아 수문학적 홍수예측 모형을 이용하여 홍수예측 업무를 수행하는데 선행시간을 충분히 확보할 수 없다는 단점을 지니고 있다. 이에 따라 본 연구에서는 기존의 하천시스템에 대한 설계 등을 목적으로 하여 모형의 적용을 통한 시뮬레이션 기법을 적용하고 이를 통하여 홍수 예경보를 발령하기에는 선행시간의 확보(대피시간의 확보)라는 측면에서 상당한 어려움을 지닐 수 있으므로 시시각각으로 측정되는 실시간 수위측정 자료 및 실시간 강우자료를 이용하여 모형의 수행과정을 생략하고 하천의 수위변동을 직접 예측하고 대피할 수 있는 시나리오 기반의 수문모형을 개발하였다. SPSS를 사용한 통계학적 모형을 대전광역시 3대 하천에 대하여 적용한 결과 예측자료가 실측자료를 고수위 및 저수위 부근에서 정확히 모의하지 못하는 경향이 나타났으나 경계 및 위험수위를 설정하고 이를 넘어가는 시점에 대한 예측을 하는 홍수경보 시점 예측에는 효율적인 적용성을 나타내었다.씬 간편하면서도 정확도가 높아서, 환경방사성 스트론튬의 정량분석에 적절히 사용될 수 있다.e form of Jones matrix, which allows a new interpretation in the conversion efficiency of the thin-film optical waveguides.있다는 장점이 있었다. 따라서 소아에서 복막투석도관 수술 시 복강경적 방법을 이용하는 것이 효율적인 복막 투석을 위해 유용하다고 생각된다.상부 방광천자에 비해 민감도 59.5%(25/42), 특이도 86.6%(13/15)였고 위양성률 13.3%(2/15), 위음성률 40.5%(17/42) 로 정확도가 낮았다. 결론 : 소변을 가리지 못하는 영유아에서 요로 감염을 진단하기 위해서는 도뇨관 채뇨에 비해 초음파 감시하 치골상부 방광천자가 정확하고 안전한 채뇨법으로 권장되어야 한다고 생각한다.應裝置) 및 운용(運用)에 별다른 어려움이 없고, 내열성(耐熱性)이 강(强)하므로 쉬운 조건하(條件下)에서 경제적(經濟的)으로 공업적(工業的) 이용(利用)에 유리(有利)하다고 판단(判斷)되어진다.reatinine은 함량이 적었다. 관능검사결과(官能檢査結果) 자가소화(自家消化)시킨 크릴간장은 효소(酵素)처리한 것이나 재래식 콩간장에 비하여 품질 면에서 손색이 없고 저장성(貯藏性)이 좋은 크릴간장을 제조(製造)할 수 있다는 결론을 얻었다.이 있음을 확인할 수 있었다.에 착안하여 침전시 슬러지층과 상등액의 온도차를 측정하여 대사열량의 발생량을 측정하고 슬러지의 활성을 측정할 수 있는 방법을 개발하였다.enin과 Rhaponticin의 작용(作用)에 의(依)한 것이며,

• Analytical Science and Technology
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• v.33 no.6
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• pp.274-284
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• 2020

This study described the analytical method for simultaneous determination of 89Sr and 90Sr in liquid sample using automated separation system. Radiostrontium in 0.5 kg of liquid sample was concentrated as SrCO3 to reduce the volume of sample, and purified from the sample using Sr-resin 2 mL (BV, Bed volume). The behavior of Sr and interferences such as Ba, Ca and Y were estimated with various flow rate ranging from 1 to 4 mL min-1. The detailed procedure for the purification of Sr on Sr-resin was presented. The purified radiostronitum was measured in Cerenkov mode and then measured in Scintillation mode by mixing scintillation cocktail. The measured value in both modes were used to calculate the activity of 89Sr and 90Sr. The performance tests were carried out the lab-control-sample having various activity ratio of between 89Sr and 90Sr. The recovery of Sr was ranged from 68 to 94 %. The relative bias of 89Sr activity was ranged from -5 to 20 %, and it was ranged from -10 to 10 % for 90Sr.