• Title/Summary/Keyword: Waste solubility

Search Result 85, Processing Time 0.024 seconds

Recovery of Nickel from Waste Pickling Solution with Column Extractor (컬럼식 연속추출장치에 의한 산세폐액중 Ni의 회수)

  • 김성규;이화영;오종기
    • 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.

  • PDF

A SYSTEMS ASSESSMENT FOR THE KOREAN ADVANCED NUCLEAR FUEL CYCLE CONCEPT FROM THE PERSPECTIVE OF RADIOLOGICAL IMPACT

  • Yoon, Ji-Hae;Ahn, Joon-Hong
    • Nuclear Engineering and Technology
    • /
    • v.42 no.1
    • /
    • pp.17-36
    • /
    • 2010
  • In this study, we compare the mass release rates of radionuclides(1) from waste forms arising from the KIEP-21 pyroprocessing system with (2) those from the directly-disposed pressurized-water reactor spent fuel, to investigate the potential radiological and environmental impacts. In both cases, most actinides and their daughters have been observed to remain in the vicinity of waste packages as precipitates because of their low solubility. The effects of the waste-form alteration rate on the release of radionuclides from the engineered-barrier boundary have been found to be significant, especially for congruently released radionuclides. the total mass release rate of radionuclides from direct disposal concept is similar to those from the pyroprocessing disposal concept. While the mass release rates for most radionuclides would decrease to negligible levels due to radioactive decay while in the engineered barriers and the surrounding host rock in both cases even without assuming any dilution or dispersal mechanisms during their transport, significant mass release rates for three fission-product radionuclides, $^{129}I$, $^{79}Se$, and $^{36}Cl$, are observed at the 1,000-m location in the host rock. For these three radionuclides, we need to account for dilution/dispersal in the geosphere and the biosphere to confirm finally that the repository would achieve sufficient level of radiological safety. This can be done only after we have known where the repository site would by sited. the footprint of repository for the KIEP-21 system is about one tenth of those for the direct disposal.

Evaluation of Low-temperature Thermal Pre-treatment and Biogas Characteristics using Waste Activated Sludge (잉여슬러지를 이용한 저온 열적전처리 및 바이오 가스 특성 평가)

  • Choi, Jae-Hoon;Jeong, Seong-Yeob;Kim, Ji-Tae
    • Journal of Korean Society on Water Environment
    • /
    • v.35 no.4
    • /
    • pp.299-307
    • /
    • 2019
  • The purpose of this study was to investigate the effect of low temperature thermal pre-treatment on biodegradation of waste activated sludge for anaerobic digestion as a countermeasure for increasing sludge generation. The experimental condition was accomplished in 2 %, 4 %, and 6 % TS concentration, and $70^{\circ}C$, $80^{\circ}C$, $90^{\circ}C$ of temperature for a maximum of 120 minutes retention time. Then, it was followed by analysis of physical/chemical properties, BMP test and composition of biogas. The biogas characteristic was evaluated by applying the modified Gomperz model. As a result, solubility of dissolved substrate, such as $SCOD_{Cr}$, soluble carbohydrate, and soluble protein, and biogas production increased as temperature increased. Solubilization efficiency at $90^{\circ}C$ was 18.4 %, 17.03 % and 16.88% in 2 %, 4 %, and 6 % TS concentration respectively. Also, solubilization rates of carbohydrate and protein similarly increased. BMP test results also showed that methane production in excess sludge increased to 0.194, 0.187 and $0.182m^3/kg$ VS. respectively, and lag phase decreased to 0.145, 0.220, 0.351 day due to acceleration of the hydrolysis step. Consequently, low-temperature thermal pre-treatment could increase biodegradability of sludge, positively affecting biogas production and sludge reduction.

Municipal Solid Waste-derived Syngas Fermentation Process by Pressurization (가압을 통한 도시형 생활 폐기물 기반 합성가스발효 공정 개발)

  • Subin Shin;Jae Hee Go;Myounghoon Moon;Min-Sik Kim;Mungyu Lee;In Seop Chang;Seongsoo Son;Gwon Woo Park
    • New & Renewable Energy
    • /
    • v.19 no.4
    • /
    • pp.35-45
    • /
    • 2023
  • Global efforts are focused on achieving carbon neutrality due to the increases in the levels of greenhouse gases. Moreover, the greenhouse gases generated from the disposal of municipal solid waste (MSW) are the primary sources of emissions in South Korea. In this study, we conducted the biological conversion of syngas (CO, H2, and CO2) generated from MSW gasification. The MSW-derived syngas was used as a feed source for cultivating Eubacterium limosum KIST612, and pressurization was employed to enhance gas solubility in culture broth. However, the pH of the medium decreased owing to the pressurization because of the CO2 in the syngas and the cultivation-associated organic acid production. The replacement of conventional HEPES buffer with a phosphate buffer led to an approximately 2.5-fold increase in acetic acid concentration. Furthermore, compared with the control group, the pressurized reactor exhibited a maximum 8.28-fold increase in the CO consumption rate and a 3.8-fold increase in the H2 consumption rate.

The SPIZWURZ project - Experimental investigations and modeling of the behavior of hydrogen in zirconium alloys under long-term dry storage conditions

  • Mirco Grosse;Felix Boldt;Michel Herm;Conrado Roessger;Juri Stuckert;Sarah Weick;Daniel Nahm
    • Nuclear Engineering and Technology
    • /
    • v.56 no.3
    • /
    • pp.824-831
    • /
    • 2024
  • In order to investigate the occurring processes during long-term dry storage of spent fuel assemblies, a joined project called SPIZWURZ, between the Karlsruhe Institute of Technology and the Gesellschaft für Anlagen-und Reaktorsicherheit (GRS), was started. Aim of the SPIZWURZ project is the determination and quantification of the influence of texture and elastic strain on diffusion and solubility of hydrogen in three different zirconium alloys used in western Europe during a long-term cooling transient (1 K/d) starting at 400 ℃. The strain in the cladding of an irradiated spent fuel rod shall be measured. Models predicting the formation of radial oriented hydrides will be validated, improved, and implemented in the GRS fuel rod performance code TESPA-ROD. This paper describes the SPIZWURZ project and already obtained first results.

${SO_4}^{2-}$ ion Removal from Solution by Crystal Precipitation on Surface Active Glasses (표면활성유리에의 결정석출을 이용한 용액중 황산염 이온 제거)

  • 남명식;김철영
    • Journal of the Korean Ceramic Society
    • /
    • v.35 no.12
    • /
    • pp.1286-1293
    • /
    • 1998
  • ${SO_4}^{2-}$ ions present in industrial waste water if combined with other metal ions in the water can cause serious scale problem in a transporting pipe. In this study therefore ${SO_4}^{2-}$ ions in an acidic solution have been removed by using surface active glasses. Glasses with various compositions of $SiO_2-Na_2O-B_2O_3-RO$ (R=Mg, Ca, Sr, Ba) system were reacted in a ${SO_4}^{2-}$ ion-containing solution with various pHs ranging from 1 to 4 for various time the reacted glass surfaces were analyzed by XRD and SEM and all ions in the reacted solution were also measured ${SO_4}^{2-}$ ions in the solution were combined with divalent ions leached out of glass and precipitated on the glass surface as sulfate crystals. In this was the surface ion could be removed from the acidic solution. The sulfate ion removal capacity is closely related to the solubility product con-stants of the newly formed sulfate crystals. Almost no sulfate crystal was formed on the MgO-containing glass while sulfate crystals were easily formed on the glass containing either SrO or BaO This indicates that those glasses have strong removal efficiency of ${SO_4}^{2-}$ ions from the solution.

  • PDF

Reuse Technology of LiCl Salt Waste Generated from Electrolytic Reduction Process of Spent Oxide Fuel (전해환원공정발생 LiCl 염폐기물 재생기술)

  • Cho, Yung-Zun;Jung, Jin-Seok;Lee, Han-Soo;Kim, In-Tae
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.8 no.1
    • /
    • pp.57-63
    • /
    • 2010
  • Layer crystallization process was tested for the separation(or concentration) of cesium and strontium fission products in a LiCl waste salt generated from an electrolytic reduction process of a spent oxide fuel. In a crystallization process, impurities (CsCl and $SrCl_2$) are concentrated in a small fraction of the LiCl salt by the solubility difference between the melt phase and the crystal phase. Based on the phase diagram of LiCl-CsCl-$SrCl_2$ system, the separation possibility by using crystallization was determined and the molten salt temperature profile during layer crystallization operation was predicted by using mathematical calculation. In the layer crystallization process, the crystal growth rate strongly affects the crystal structure and therefore the separation efficiency. In the conditions of about 20-25 l/min cooling air flow rate and less than 0.2g/min/$cm^2$ crystal flux, the separation efficiency of both CsCl and $SrCl_2$ showed about 90% by the layer crystallization process, assuming a LiCl salt reuse rate of 90wt%.

Preparation and Characterization of the Hydrolyzed Protein from Shaving Scraps of Leather Waste Containing Chromium by the Combination Treatment with Alkaline Inducing Agent and Alkaline Proteolytic Enzyme (Alkaline Inducing Agent 및 Alkaline Proteolytic Enzyme 혼용처리에 의한 Shaving Scraps 가수분해 단백질의 제조 및 특성)

  • Kim, Won-Ju;Cho, Ju-Sik;Lee, Hong-Jae;Heo, Jong-Soo
    • Journal of the Korea Organic Resources Recycling Association
    • /
    • v.6 no.1
    • /
    • pp.1-12
    • /
    • 1998
  • To examine the possibility of protein recycling of shaving scraps containing chromium generated from manufacturing process of leather, the optimum hydrolysis conditions and the withdrawal methods of low molecular weight protein for using the liquid fertilizer sources by investigation of solubilities of hydrolyzed protein, inorganic nutrients contents and molecular weight distributions of hydrolyzed protein from shaving scraps treated with mixed alkaline inducing agents and mixed alkaline proteolytic enzymes including MgO were investigated. In hydrolysis of shaving scraps treated with mixed alkaline inducing agents, the solubility of shaving scraps were clearly different with 65~85% according to the sorts of the inducing agents, and the degree of hydrolysis was high in the order of NaOH, $Ca(OH)_2$ and KOH. The average molecular weights of withdrawal hydrolyzed protein were 10, 40 and 80 KD treated with NaOH, $Ca(OH)_2$ and KOH, respectively. And the chromium contents was about 15 ppm. In hydrolysis of shaving scraps treated with mixed alkaline proteolytic enzymes, the bility of shaving scraps were high in the order of alcalase, esperase and savinase. In c of treating 0.5% alcalase, the low molecular weight of hydrolyzed protein could be withdrawn. The solubility of the hydrolyzed protein was about 85%, the average molecular weight of the protein was below 1 KD and chrome content of the protein was below 10 ppm.

  • PDF

Extraction of nitrate salts from de-NOx waste scrubbing solution (탈질 스크러버의 폐세정액으로부터 질산염 추출 연구)

  • Kim, Wooram;Ha, Taeyoung;Park, Yeonsoo;Lee, Hyunsuk;Jo, Youngmin
    • Journal of the Korean Applied Science and Technology
    • /
    • v.34 no.2
    • /
    • pp.210-216
    • /
    • 2017
  • Recovery of low level nitric acid and sulfuric acid ions, which were contained in wastewater of a wet scrubber for de-NOx and de-SOx from ship engines, was attempted as fertilizing materials. This study utilized a selective extraction method using four organic solvents to precipitate the solid salts of ammonium nitrate and ammonium sulfate. The IR analysis showed almost same composition of the extracted ammonium salts with a commercial product, and recovery rate of nitrogen and sulfuric ions was 89% and 80% respectively. It was found that the selectivity and solubility consequently could be the crucial factors to recover the low level ions from the waste scrubbing water.

Study on the Simulation of Crud Formation using Piping Materials of Nuclear Power Plant in High Temperature Water (원자력 발전소 배관재를 이용한 고온 수화학 조건에서의 방사화 부식생성물 모사에 관한 연구)

  • Kim Sang Hyun;Kim In Sup;Lee Kun Jai
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.3 no.1
    • /
    • pp.31-40
    • /
    • 2005
  • High temperature - high pressure apparatus was developed to simulate nickel fewite corrosion products which were main compositions of the radioactive crud in the nuclear power plant. Corrosion product similar to the crud was obtained by a tube accumulator system. Nickel alloy (Inconel 690) and carbon steel (SA106 Gr. C) were corroded at 270 $\^{circ}C$ in the corrosion product generator. Ni ions and Fe ions dissolved by corrosion reaction were able to be transported to the accumulator because the crud generation mechanism was the solubility change with temperature. To evaluate the properties of simulated corrosion products, scanning electron microscope (SEM) observation and EDAX analysis were performed. SEM observation of corrosion product showed the needlelike or crystal structure of oxide depending on precipitating location. The crystal oxide was the nickel ferrite, which was similar to the crud in nuclear power plants.

  • PDF