• 자원리싸이클링
• /
• 제24권5호
• /
• pp.33-39
• /
• 2015

음이온 교환막을 이용한 확산투석에 의해 폐솔더 박리액으로부터 질산을 효율적으로 회수하기 위한 기초 연구를 실시하였다. 우선 모의용액 실험의 경우 유속, 유속비, 질산농도, 금속이온 종류 및 농도 등이 질산 회수율에 미치는 영향을 조사하였다. 유속이 증가함에 따라 질산 회수율은 감소하였고 급액에 대한 순수의 유속비(W/F)가 증가할수록 질산 회수율은 증가하여 유속비가 1.5이상에서 약 99%의 질산 회수율을 보였다. 급액중 질산용액의 농도가 증가함에 따라 3.0 M 까지는 산회수율이 증가 하였으나 3.0 M 이후로는 회수율은 점차 낮아 졌다. 확산투석막을 통과하는 금속이온의 투과율은 Pb, Na, Cu순 이었고, Fe과 Sn은 투과되지 않았다. 실제 폐솔더액을 사용하여 유속 $0.9L/hr-m^2$, W/F = 1.3 으로 확산 투석을 실시한 결과 약 94%의 질산 회수율을 얻을 수 있었다.

• 한국토양환경학회지
• /
• 제3권1호
• /
• pp.31-44
• /
• 1998

본 연구는 중금속원소의 주오염원 중의 하나인 금속폐광산에 다량 잔존하는 폐석을 효율적으로 처리하기 위해 실내모형시험을 수행하였으며, 그 결과를 광산폐석처리의 기술개발에 기초자료로 활용하고자 한다. 실험의 도구는 실험결과에 거의 영향이 없는 내산성 내알카리성의 아크릴산수지와 폴리에틸렌 관을 사용하였다. 본 연구에서 제작 운용된 8개의 모형을 계내의 환경, 충진물의 배열방식 및 종류 등으로 분류한다면 4개의 그룹으로 나눌 수 있다. 그룹 1은 계내에 폐석으로만 충진하여 개방계에서 실험한 배경모델이고, 그룹 2는 각각 두 개의 폐석층과 석회암편층을 층상으로 배열한 뒤 개방계와 폐쇄계로 구분하여 실험하였다. 그룹 3은 폐석과 석회암편을 골고루 잘 섞어 계내에 충진하고(혼합모델)이를 개방계와 폐쇄계로 구분하여 실험하였으며, 마지막 그룹 4는 폐석층의 표층부에 석회암편층을 가하여 실험하였다. 배경모델인 모델 Ⅰ로부터 배수된 시수는 실험초기부터 말기까지 중금속원소의 용존량이 매우 높다. 그런, 다른 모델에 비해 그룹 3에 해당되는 모델 Ⅴ와 Ⅶ은 중금속원소의 함량이 매우 낮아 제거효과가 가장 높은 것으로 나타났다. 폐쇄된 혼합모델에서 폐석과 석회암편의 혼합비를 1:1, 2:1로 달리하더라도 중금속원소의 제거효과 는 대동소이한 것으로 나타났다. 그러나, 계내를 같은량의 충진물로 충진하더라도 혼합모델은 층상모델에 비해 중금속원소의 제거효과가 현저히 높다. 그리고, 다른 실험조건이 같은 폐쇄계와 개방계를 비교하면 전자의 중금속원소의 제거효과가 다소 높은 것으로 나타났다.

• Carbon letters
• /
• 제7권3호
• /
• pp.180-187
• /
• 2006

The treatment of piggery wastes was carried out at pilot scale using a multilayered metal-activated carbon system followed by carbon bed filtration. The physicochemical properties were obtained from treated samples with aqueous solutions containing metallic ions such as $Ag^+$, $Cu^{2+}$, $Na^+$, $K^+$ and $Mn^{2+}$, which main obsevations are subjected to inspect surface properties, color removal properties by Uv/Vis and EDX. Multilayered metal-activated carbons were contacted with waste water to investigation of the simultaneous catalytic effect for the COD, BOD, T-N and T-P removal. The removal results for the piggery waste using multilayered metal-activated carbon bed was achieved the satisfactory removal performance under permitted values of Ministry of Environment of Korea. The high efficiency of the multilayered metal-activated carbon bed was determined by the performance of this material for trapping, catalytic effect and adsorption of organic solid particles.

• 자원환경지질
• /
• 제30권2호
• /
• pp.123-135
• /
• 1997

In order to investigate the dispersion patterns and contamination level of heavy metals in the soil-ecosystem and to evaluate the efficiency of soil remediation by reversed soil method, soils and plants were collected from the Dongjin Au-Ag-Cu mine area and analysed for heavy metals. The dispersion patterns of heavy metals in soils and plants show that heavy metal pollutions caused by waste rump around Dongjin mine are mainly found in the vicinity of the waste rump and in the southward slanting of mine. Toxic metallic pollutants from the mine influence heavy metal contents in paddy soils in downstream area, and may be a potential sources of heavy metal pollution on crop plants. Soil samples collected from the remediated rice farming field by reversed method show similar levels of heavy metal content to those from the polluted rice farming field, but topsoil enrichment of heavy metals are not found. Heavy metal contents of the rice plants collected from remediated rice farming field are significantly lower than those from polluted rice farming field, and it suggests that the reversed soil method is effective for the reduction of bioavailability of heavy metals.

• 한국지하수토양환경학회:학술대회논문집
• /
• 한국지하수토양환경학회 2005년도 총회 및 춘계학술발표회
• /
• pp.363-370
• /
• 2005

There are approximately 2,000 metallic mines which have been abandoned in Korea. Most of the mines are located in the watershed area, which is main source of drinking water for Seoul Metropolitan area. Untreated mining wastes are remained around abandoned mines in study area. These mining wastes, flowing into farmland and stream in the downstream of abandoned mines, would cause water and soil pollution. The mining waste samples from Guedo mine, Manjung mine and Joil mine recently abandoned were collected for the evaluation of the potential of water pollution by mine waste. Index of geoaccumulation($M\"{u}ller$, 1979), fractional composition and removal efficiency of some heavy metals by different concentration of HCl treatment were analyzed. Index of geoaccumulation of Cd, Pb, Zn, Cu, Ni and Cr are 6, $4{\sim}6,\;0{\sim}6,\;4{\sim}5$, 2 and 0 respectively. Index of geoaccumulation of Cd, Pb, Zn and Cu reveals the mining wastes has high pollution pottential in the area. Organic fraction of Cu, reducible fraction of Pb, residual fraction of Ni and Zn were the most abundant fraction of heavy metals in mining wastes.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2003년도 가을 학술논문집
• /
• pp.358-362
• /
• 2003

산화물 형태의 사용후핵연료를 용융염에서 금속 형태로 전환하여, 발열량, 부피 및 방사능을 1/4로 감소시킬 수 있는 전기화학적 금속전환 공정을 개발하고, 5kg $U_3O_8$/Batch 규모의 mock-up 실험을 수행하였다. 본 연구에서는 전해 셀의 운전변수를 해석하였으며, 아울러 hot test를 위한 장치개발 연구도 병행하였다. 전기화학적 금속전환 공정을 이용하여 $U_3O_8$ 형태의 천연우라늄 분말을 99% 이상 금속전환할 수 있었으며, 또한 20kg $U_3O_8$/batch 규모 장치의 설계자료를 산출할 수 있었다.

• 방사성폐기물학회지
• /
• 제18권3호
• /
• pp.415-420
• /
• 2020

Strontium is known as a salt-soluble element during the electrolytic oxide reduction (EOR) process. The chemical behavior of SrO during EOR was investigated via thermodynamic calculations to provide quantitative data on the chemical status of Sr. To achieve this, thermodynamic calculations were conducted using HSC chemistry software for various EOR conditions. It was revealed that SrO reacts with LiCl salt to produce SrCl₂, even in the presence of Li₂O, and that the ratio of SrCl₂ depends on the initial concentration of Li₂O dissolved in LiCl. It was found that SrO reacts with Li to produce Sr during EOR and that the reduced Sr reacts with LiCl salt to produce SrCl₂. As a result, the proportions of metallic forms were lower in Sr than in La and Nd under various EOR conditions. The thermodynamic calculations indicated that the three chemical forms of SrO, SrCl₂, and Sr co-exist in the EOR system under an equilibrium with Li, Li₂O, and LiCl.

• 방사성폐기물학회지
• /
• 제19권1호
• /
• pp.39-49
• /
• 2021

The behaviors of various desorption agents were investigated during the desorption of cesium (Cs) from samples of clay minerals and actual soil. Results showed that polymeric cation exchange agents (polyethyleneimine (PEI)) efficiently desorbed Cs from expandable montmorillonite, whereas acidic desorption solutions containing HCl or PEI removed considerable Cs from hydrobiotite. However, most desorption agents could desorb only 54% of Cs from illite because of Cs's specific adsorption to selective adsorption sites. Cs desorption from an actual soil sample containing Cs-selective clay mineral illite (< 200 ㎛) and extracted from near South Korea's Kori Nuclear Power Plant was also investigated. Considerable adsorbed 137Cs was expected to be located at Cs-selective sites when the 137Cs loading was much lower than the sample's cation exchange capacity. At this low 137Cs loading, the total Cs amount desorbed by repeated washing varied by desorption agent in the order HCl > PEI > NH4+, and the highest Cs desorption amount achieved using HCl was 83%. Unlike other desorption agents with only cation exchange capabilities, HCl can attack minerals and induce dissolution of metallic elements. HCl's ability to both alter minerals and induce H+/Cs+ ion exchange is expected to promote Cs desorption from actual soil samples.

• 자원환경지질
• /
• 제28권3호
• /
• pp.231-241
• /
• 1995

It is well known that hydroxyapatite [$Ca_{10}(PO_4)_6(OH)_2$] have an exchangeability for various heavy metal ions in aqueous solution. To evalute the feasibility of employing the synthetic hydroxyapatites as an eliminatable exchanger for environmentally noxious caions in waste water, the adsorption properties, the removal capacities and the selectivity of the apatites for various cations were investigated in more detailed. The heavy metal cations have been exchanged in calcium part of hydroxyapatite. The order of the degree of amount exchanged of the investigated cations is $Pb^{2+}>Cd^{2+}>Zn^{2+}>Ba^{2+}$. The molar ratios between released $Cd^{2+}$ ions and remeved divalent metal cations in the reacted solution with hydroxyapatite are roughly close to an integer 1.0, suggesting that an ion-exchange reaction could have played a major role in the removal of heavy metals rather then an adsorption effect. The exchangeability of the hydroxyapatite powder of Ca/P molar ratio 1.67, which have specipic surface area of $104.5m^2g^{-1}$, appeared to be better then $237.6{\mu}g$ per g for $Pb^{2+}$ ions. The removal capacity of the heavy metal ions varies directly as particle size of hydroxyapatites. All evidences obtained indicate that the synthesized hydroxyapatite powders by precipitation reaction method can be employed as an effective cation exchanger for eliminating noxious ions in waste water even in some improvemental.

• 대한전자공학회:학술대회논문집
• /
• 대한전자공학회 2001년도 The 6th International Symposium of East Asian Resources Recycling Technology
• /
• pp.179-182
• /
• 2001

The chloride volatilization method for the recovery of zirconium and removal of uranium from zirconium containing metallic wastes formed in spent fuel reprocessing was studied using the simulated alloy waste, i.e. the mixture of Zr foil and UO$_2$/U$_3$O$_{8}$ powder. When the simulated waste was heated to react with chlorine gas at 350- l00$0^{\circ}C$, the zirconium metal changed to volatile ZrCl$_4$showing high volatility ratio (Vzr) of 99%. The amount of volatilized uranium increases at higher temperatures causing lowering of decontamination factor (DF) of uranium. This is thought to be caused by the chlorination of UO$_2$ with ZrCl$_4$vapor. The highest DF value of 12.5 was obtained when the reaction temperature was 35$0^{\circ}C$. Addition of 10 vol.% oxygen gas into chlorine gas was effective for suppressing the volatilization of uranium, while the volatilization ratio of zirconium was decreased to 68% with the addition of 20 vol.% oxygen. In the case of the mixture of Zr foil and U$_3$O$_{8}$, the V value of uranium showed minimum (44%) at 40$0^{\circ}C$ with chlorine gas giving the highest DF value 24.3. When the 10 vol.% oxygen was added to chlorine gas, the V value of zirconium decreased to 82% at $600^{\circ}C$, but almost all the uranium volatilized (Vu=99%), which may be caused by the formation of volatile uranium chlorides under oxidative atmosphere.ere.