• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.06a
• /
• pp.284-289
• /
• 2005

According to the nuclear safety regulation policy including the administration of radionuclides in low level radwastes, the evaporator bottoms were mixed with cement to form a stable solidification for identifying the recovery possibility of the C-14. The chemical oxidation method was applied for the extraction of C-14 from the cement waste form. The emitting beta ray of the C-14 extracted from the radwastes was measured with the liquid scintillation counter and calculated by using the quenching correction curves. Only the beta emitting radioactive nuclides of the C-14 in the radwastes was showed the radioactivities with the range of $2.7E+00\;{\sim}\;3.07E+02$ Bq/g.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2007.11a
• /
• pp.107-108
• /
• 2007

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2010.05a
• /
• pp.115-116
• /
• 2010

방사성농축폐액처리를 위한 Polymer-Modified-portlandcement 고화체는 Polymer 및 시멘트, 물을 혼합매질로 제조되며 농축폐액처리를 위해 Emulsion Polymer를 사용하였으며 PMC 고화체의 물성을 평가하기위한 고화체의 제조에서 이들 매질의 최적혼합비를 찾기 위해 Polymer 및 물, 시멘트의 혼합비를 1/1/2,1/2/4,1/3/9 등 혼합비에 따른 시편 및 Polymer 첨가량의 증가에 따라 함유비를 달리하는 시편을 제조하여 경화시간별 압축강도를 측정하였으며 매질의 최적혼합비 및 폴리머의 투입비를 구하고자하였다. 특성평가시험을 위한 시편으로는 직경 50, 높이 100mm(L/D=2) 인시편을 제조하여 압축강도를 측정하였으며 폴리머와 시멘트의 결합상태를 확인하기위해 SEM사진을 통한 미세구조를 관찰하였으며 시험결과 P/W/C의비가 1/3/9인 혼합비시편의 압축강도가 $343.36Kg_f/cm^2$로 가장 높았으며 폴리머의 함유량을 달리한 시험에서는 7%폴리머 함유시편은 $397.24Kg_f/cm^2$, 20% 폴리머함유시편은 $175.36Kg_f/cm^2$으로 폴리머의 함유량이 7~15% 이내의 폴리머함유고화체가 적합한 것으로 판단되었으며 폴리머의 투입양이 증가할수록 압축강도가 감소하였으며 경화시간도 최소4주이상 되어야하는 것으로 판단되었다.

• Proceedings of the KIEE Conference
• /
• 2009.07a
• /
• pp.1823_1824
• /
• 2009

원자력 발전소 운전과정에서 발생하는 각종 폐액은 저장/여과 과정을 거치게 된다. 이러한 폐액의 저장/여과 과정에서 탱크 내에 침적된 방사성 슬러지들은 농축 고화 처리가 요구 되며 방사선량에 따라 작업자의 접근이 제한적이다. 본 논문에서는 탱크나 섬프(Sump)내의 방사성 슬러지를 제거하기 위하여 개발 중인 로봇의 기능과 이를 이용한 슬러지 제거 기초실험 결과를 제시한다.

• Nuclear Engineering and Technology
• /
• v.27 no.2
• /
• pp.260-268
• /
• 1995

국내 원자력발전소의 방사성폐기물 발생량은 초고압 압축, 농축폐액 건조, 페수지 건조 등의 폐기물감용을 위한 운영계획이 수립되고 또한 일부 원자력발전소에서는 1995년부터 운영이 시작될 예정이어서 감소가 예상되고 있다. 원자력발전소로부터 방사성폐기물의 누적량은 2035년까지 운영자의 폐기물 감용 계획을 고려한다면 141,920 드럼으로 예상할 수 있고, 이에 상응하는 방사능량은 반감기가 한달 이상인 30개 핵종에 대하여 방사성 붕괴를 무시할 때 49,390 Ci였다. 특히 원자력환경관리센터에서 수행한 개념설계에 따른 1차 건설예정의 지하 처분동굴의 적재량인 약 10만 드럼은 2014년까지 누적량으로 채울 수 있고 이때 처분장의 장기적 성능평가에 주요 고려 대상인 반감기가 5년 이상의 14개 핵종에 대한누적 방사능량은 약 13,577 Ci였다. 이 예측된 발생량과 재고량은 처분장 장기적 성능 및 안전성 평가에 중요한 기초자료가 될 것이다.

• Journal of Radiation Protection and Research
• /
• v.10 no.2
• /
• pp.113-121
• /
• 1985

For the safety assessment of radwaste treatment and disposal, the leaching characteristics of $Cs^+\;and\;Sr^{++}$ from the cement-solidified radwastes was investigated by means of the survey and analysis of the activity leach rate and cumulative leach fraction of $^{137}Cs\;and\;^{90}Sr$ leaching from solidified radwastes. The cylindrical cement-solidified samples were made by the sodium silicate method and neutralization method changing the mole density of simulated liquid radwaste, type of cement, adding material and concentration of boric acid. The leaching study was carried out by the method using simulated PWR concentrated liquid radwaste solidified in cement that had been processed following the recommendations of IAEA. All the experimental results are in well accordance with the research data reported previously, but the watertight cement-solidified radwastes show rather high leach rate of radioactivity. It is learned, therefore, that the watertight cement is not adequate as the material for the solidified radwastes.

• Resources Recycling
• /
• v.21 no.2
• /
• pp.53-58
• /
• 2012

A laboratory study was carried out to recover KI crystals with high purity from a waste solution generated from the production of polarizing film for LCD industry. The waste solution contains 1 to 4% KI, and other impurities such as B, PVA and etc. More than 95% purity of KI crystals were produced through refining process such as vacuum evaporation and fractional crystallization. Most of B compounds and impurities were removed by concentrating the waste solution until KI content reached about 50%. The KI crystals were washed with solvents to remove most of PVA which gave result in producing 99.5% purity of crystals. The overall recovery of KI was about 90% during the concentration process.

• Applied Chemistry for Engineering
• /
• v.26 no.3
• /
• pp.270-274
• /
• 2015

We develop advanced oxidation processes for the treatment of spent electroless nickel plating solution. Apart form recovering nickel by leaching and enrichment, more emphasis is placed on rendering the waste water recyclable via oxidizing phosphite and hypophosphite into phosphate which can then be precipitated easily. $UV/H_2O_2$ process is employed and the conversion efficiency of COD and $PO_4-P$, and $H_2O_2$ consumption are analyzed. Furthermore, the $UV/H_2O_2/O_3$ process in conjunction with $O_3$ generator enables us to not only save the treatment time by 6 hours but also reduce $H_2O_2$ consumption by 30%.

• Resources Recycling
• /
• v.7 no.1
• /
• pp.27-33
• /
• 1998

A study on thc recovcry oi nickel from waste pickling solutions removed li-ee nil~ica cid and hydmflnoric acid is carried out with pulsed column extractor for thc industrial application. The ~esults show that thc Iron and chromium arc efteclively elunmatcd from the waste solution by precipitalion as the form of hydraxidc with thc adjustment of pH with CaCO;, whlle the nickel is not prcc~pitatcd. Thc cxlraction eficicncy ol nickel with column cxtraclor generally improves 8s the pulse velosity (product of amplmde and frequency) incrcascs, optimum pcrfarmancc typically occuring slightly below an amplihldefrecluency product which results in flooding the column because of excessive emulsiIicalian And the nickel loaded in the organic is erfeclively conce~~trtratebdy ZM H2S0,, ~ I It he stlipping stage. The solubility of NiSO, in the H,SO, solution dccreaaes w~th thc higher H,SO, concentralion and appears to be 55 grL in the 2M HSO* solulian.

• Korean Chemical Engineering Research
• /
• v.60 no.4
• /
• pp.473-477
• /
• 2022

In this study, candidate technologies for lithium recovery from the process waste liquid generated in the waste battery recycling process were reviewed, and technologies applicable to the process from the commercialization point of view were reviewed from a qualitative point of view. The evaporation method is difficult to apply because it requires a large-scale land and shows a low recovery rate due to the loss of Li during the concentration process. In the case of precipitation, a commercially available technology shows a high recovery rate due to the high Li/Na selectivity of phosphoric acid, but there are disadvantages in that the process is complicated due to the use of expensive phosphoric acid, requiring a recovery step, and continuous operation is impossible because solids are handled in the Li concentration process. In the case of solvent extraction, if we find an inexpensive extractant with high Li/Na selectivity, continuous operation is possible with the method used in extraction of other metals in the previous step, and when Li is concentrated, continuous operation is possible because it is in a liquid state. If it shows a similar recovery rate compared to precipitation technology, commercialization will be the most likely.