• 제목/요약/키워드: radioactive ions

검색결과 118건 처리시간 0.022초

옥천대(沃川帶) 우라늄광층(鑛層)의 구조규제(構造規制) 및 지구화학적(地球化學的) 특성연구(特性硏究) (Lithologic and Structural Controls and Geochemistry of Uranium Deposition in the Ogcheon Black-Slate Formation)

  • 이대성;윤석규;이종혁;김정택
    • 자원환경지질
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    • 제19권spc호
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    • pp.19-41
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    • 1986
  • Structural, radioactive, petrological, petrochemical, mineralogical and stable isotopic study as well as the review of previous studies of the uranium-bearing slates in the Ogcheon sequence were carried out to examine the lithological and structural controls, and geochemical environment in the uranium deposition in the sequence. And the study was extended to the coal-bearing formation (Jangseong Series-Permian) to compare the geochemical and sedimentologic aspects of uranium chemistry between Ogcheon and Hambaegsan areas. The results obtained are as follows: 1. The uranium mineralization occurs in the carbonaceous black slates of the middle to lower Guryongsan formation and its equivalents in the Ogcheon sequence. In general, two or three uranium-bearing carbonaceous beds are found with about 1 to 1.5km stratigraphic interval and they extend from Chungju to Jinsan for 90km in distance, with intermittent igneous intrusions and structural Jisturbances. Average thickness of the beds ranges from 20 to 1,500m. 2. These carbonaceous slate beds were folded by a strong $F_1$-fold and were refolded by subsequent $F_1$-fold, nearly co-axial with the $F_1$, resulting in a repeated occurrence of similar slate. The carbonaceous beds were swelled in hing zones and were shrinked or thined out in limb by the these foldings. Minor faulting and brecciation of the carbonaceous beds were followed causing metamorphism of these beds and secondary migration and alteration of uranium minerals and their close associations. 3. Uranium-rich zones with high radioactive anomalies are found in Chungju, Deogpyong-Yongyuri, MiwonBoun, Daejeon-Geumsan areas in the range of 500~3,700 cps (corresponds to 0.017~0.087%U). These zones continue along strike of the beds for several tens to a few hundred meters but also discontinue with swelling and pinches at places that should be analogously developed toward underground in their vertical extentions. The drilling surveyings in those area, more than 120 holes, indicate that the depth-frequency to uranium rich bed ranging 40~160 meter is greater. 4. The features that higher radioactive anomalies occur particularly from the carbonaceous beds among the argillaceous lithologic units, are well demonstrated on the cross sections of the lithology and radioactive values of the major uranium deposits in the Ogcheon zone. However, one anomalous radioactive zone is found in a l:ornfels bed in Samgoe, near Daejeon city. This is interpreted as a thermal metamorphic effect by which original uranium contents in the underlying black slate were migrated into the hornfels bed. 5. Principal minerals of the uranium-bearing black slates are quartz, sericite, biotite and chlorite, and as to chemical composition of the black slates, $Al_2O_3$ contents appear to be much lower than the average values by its clarke suggesting that the Changri basin has rather proximal to its source area. 6. The uranium-bearing carbonaceous beds contain minor amounts of phosphorite minerals, pyrite, pyrrhotite and other sulfides but not contain iron oxides. Vanadium. Molybdenum, Barium, Nickel, Zirconium, Lead, Cromium and fixed Carbon, and some other heavy metals appear to be positive by correlative with uranium in their concentrations, suggesting a possibility of their genetic relationships. The estimated pH and Eh of the slate suggests an euxenic marine to organic-rich saline water environment during uranium was deposited in the middle part of Ogcheon zone. 7. The Carboniferous shale of Jangseong Series(Sadong Series) of Permian in Hambaegsan area having low radioactivity and in fluvial to beach deposits is entirely different in geochemical property and depositional environment from the middle part of Ogcheon zone, so-called "Pibanryong-Type Ogcheon Zone". 8. Synthesizing various data obtained by several aspects of research on uranium mineralization in the studied sequence, it is concluded that the processes of uranium deposition were incorporated with rich organic precipitation by which soluble uranyl ions, $U{_2}^{+{+}}$ were organochemically complexed and carried down to the pre-Ogcheon sea bottoms formed in transitional environment, from Red Sea type basin to Black Sea type basin. Decomposition of the organic matter under reducing conditions to hydrogen sulfide, which reduced the $UO{_2}^{+2}$ ions to the insoluble uranium dioxide($UO_2$), on the other side the heavy metals are precipitated as sulfides. 9. The EPMA study on the identification of uraninite and others and the genetic interpretation of uranium bearing slates by isotopic values of this work are given separately by Yun, S. in 1984.

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원전 폐콘크리트의 방사성 폐기물 처분용 고화제로의 활용을 위한 고화체 특성 평가 (Characteristics Evaluation of Solidifying Agent for Disposal of Radioactive Wastes Using Waste Concrete Powder)

  • 서은아;이호재;권기현;김도겸
    • 한국건설순환자원학회논문집
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    • 제9권4호
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    • pp.451-459
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    • 2021
  • 이 연구에서는 원전 해체 콘크리트에서 분리된 폐콘크리트 미분말을 방사성 폐기물용 고화제로 재활용하기 위한 성능평가를 수행하였다. 원전 해체 콘크리트에서 분리된 폐콘크리트 미분말을 모사한 시료를 제작하였으며, 주요 변수는 결합재 종류와 제올라이트 혼입율이었다. 고화제 특성평가는 유동성과 압축강도 및 비방사성 세슘에 대한 침출 저항성을 수행하였다. 폐콘크리트 모사시료의 압축강도는 제올라이트 혼입율이 증가함에 따라 증가하였으며, 제올라이트가 5% 이상 혼입된 고화제는 인수기준 대비 1.4~1.7배 높은 압축강도를 나타내었다. 모든 시험체의 세슘 침출지수는 6 이상으로 인수기준을 만족하였으며, SA의 침출지수는 OPC 대비 1.47~1.63배 높게 나타났다. 특히, 제올라이트 5% 치환 고화제의 28일 이후 평균 침출지수는 9.15으로 OPC 대비 약 6.4% 향상되었으며, 전 기간 동안 안정적인 성능을 나타내어 제올라이트가 세슘이온에 대한 침출저항성 향상에 효과적임을 확인하였다.

PWR 사용후핵연료 중 Zr 및 Zr 동위원소 정량을 위한 분리 및 정제 (Separation and Purification for the Determination of Zirconium and Its Isotopes in PWR Spent Nuclear Fuels)

  • 김정석;전영신;박용준;이창헌;김원호
    • 분석과학
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    • 제11권6호
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    • pp.421-428
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    • 1998
  • 사용후핵연료의 화학특성을 규명하기 위하여 시료 중에 함유되어 있는 핵분열생성물 중 Zr을 분리, 정제하는 연구를 수행하였다. 우라늄과 핵분열생성물 대신 비방사성 금속이온들로 구성된 사용후핵연료 모의 용해용액을 시료로 사용하였다. 12 M HCl 용액으로 전처리한 Dowex $1{\times}8$ 음이온교환수지관에서 Ce, Nd, Cs, Rb, Ba, Sr, Ru, Rh, Pd, Ag 및 Cd을 용리시킨 후 5 M HCl 용액으로 Zr을 95% 이상 분리, 회수할 수 있었다. 용출액에 함유되어 있는 Zr 동위원소의 동중원소인 Mo을 제거하기 위하여 5 M HCl 용액으로 전처리한 Dowex $1{\times}8$ 음이온교환수지관에서 정제하였으며, 실제 PWR 사용후핵연료에 함유되어 있는 Zr 분리, 정제에 적용하여 질량분석한 결과 Mo 및 Sr에 의한 동중원소 영향이 나타나지 않았다.

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Adsorption behavior of platinum-group metals and Co-existing metal ions from simulated high-level liquid waste using HONTA and Crea impregnated adsorbent

  • Naoki Osawa;Seong-Yun Kim;Masahiko Kubota;Hao Wu;Sou Watanabe;Tatsuya Ito;Ryuji Nagaishi
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.812-818
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    • 2024
  • The volume and toxicity of radioactive waste can be decreased by separating the components of high-level liquid waste according to their properties. An impregnated silica-based adsorbent was prepared in this study by combining N,N,N',N',N",N"-hexa-n-octylnitrilotriacetamide (HONTA) extractant, N',N'-di-n-hexyl-thiodiglycolamide (Crea) extractant, and macroporous silica polymer composite particles (SiO2-P). The performance of platinum-group metals adsorption and separation on prepared (HONTA + Crea)/SiO2-P adsorbent was then assessed together with that of co-existing metal ions by batch-adsorption and chromatographic separation studies. From the batch-adsorption experiment results, (HONTA + Crea)/SiO2-P adsorbent showed high adsorption performance of Pd(II) owing to an affinity between Pd(II) and Crea extractant based on the Hard and Soft Acids and Bases theory. Additionally, significant adsorption performance was observed toward Zr(IV) and Mo(VI). Compared with studies using the Crea extractant, the high adsorption performance of Zr(IV) and Mo(VI) is attributed to the HONTA extractant. As revealed from the chromatographic experiment results, most of Pd(II) was recovered from the feed solution using 0.2 M thiourea in 0.1 M HNO3. Additionally, the possibility of recovery of Zr(IV), Mo(VI), and Re(VII) was observed using the (HONTA + Crea)/SiO2-P adsorbent.

동전기적방법을 이용한 TRIGA 연구로 주변 토양내의 세습과 코발트 제거 (Removal of Cesium and Cobalt within Soil around TRIGA Reactor by Electrokinetic method)

  • 김계남;원희준;정종헌;오원진
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 학술논문집
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    • pp.13-23
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    • 2004
  • 동전기적방법을 사용하여 TRIGA 연구용 원자로 주변 세슘 및 코발트제거 특성을 분석하고 토양컬럼 내의 pH 상승을 제거할 수 있는 방안을 제시했다. 전기장을 높이기 위해 NaCl 용액이 전해질로 사용되었을 때, 토양컬럼 음극주변에 침전물이 형성되어 낮은 제거효율을 나타냈다. 그래서, pH의 상승을 억제하기 위해 초산완충액을 토양컬럼에 주입하고, 초산을 주기적으로 음극저수조에 주입했다. 초기제염기간 동안 전기삼투보다는 전기이동에 의해 많은 세슘과 코발트가 제거되었다. 토양컬럼 내의 총 세슘 중 96%가 5.9 일 동안 제거되었고, 총 코발트 중 94%가 제거되었다. 또한, 개발된 모델에 의한 시뮬레이션 결과는 실험결과와 거의 일치했다.

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칼슘이 용출된 콘크리트의 공극 구조 및 강도 특성 (Characteristics of Pore Structures and Compressive Strength in Calcium Leached Concrete Specimens)

  • 양은익;최윤석
    • 콘크리트학회논문집
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    • 제23권5호
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    • pp.647-656
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    • 2011
  • 방사성 폐기물 처분 시설과 같은 지하 구조물의 콘크리트 부재가 장기간에 걸쳐 지하수(이온교환수)와 접촉하면 이온교환수와 공극수 사이에 농도구배가 발생한다. 이로 인해 공극수로부터 칼슘이온이 용출되고, 콘크리트의 열화가 진행된다. 따라서 이 연구에서는 콘크리트의 칼슘 용출에 의한 내부공극 구조의 변화를 분석하고, 열화된 콘크리트의 강도 특성을 평가하고자 하였다. 연구 결과, 콘크리트의 칼슘이온이 용출됨에 따라 50~500 nm 크기의 공극들이 상당히 증가하게 되며, 용출 초기에는 200 nm 크기 이상의 공극들이 급격히 증가하고 이후에는 200 nm 크기 이하의 공극들이 증가하는 것으로 나타났다. 칼슘이 용출된 두께가 증가함과 더불어 압축강도는 감소하였으며, 칼슘이 용출된 OPC 콘크리트의 잔류강도는 대략 33~58% 정도로 나타났다.

모의 방사성 폐액에서 아스코르빈산에 의한 Pd의 침전 분리 (Separation of Palladium Precipitate Formed by Ascorbic Acid in a Simulated Radioactive Liquid Waste)

  • 황두성;권선길;이규일;박진호;유재형;박소진
    • 공업화학
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    • 제9권2호
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    • pp.243-248
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    • 1998
  • 본 연구에서는 아스코르빈산을 이용하여 다성분계(Pd, Ru, Rh, Nd, Cs, Sr, Fe, Ni, Zr, Mo)의 모의고준위폐액 내에 있는 Pd의 침전 분리와 침전물의 특성이 조사되었다. 아스코르빈산의 금속이온들에 대한 환원특성을 이용하여 다성분계 모의폐액 내에 함유된 Pd을 선택적으로 침전 분리할 수 있었으며, 질산농도 0.5 M에서는 0.04 M의 아스코르빈산을 첨가함으로써 99.5% 이상의 Pd을 침전 분리시킬 수 있었다. 아스코르빈산에 의한 Pd 이온의 환원 반응은 질산농도가 중요한 역할을 하며, 질산농도가 증가할수록 Pd의 침전율은 감소하였다. 용액의 질산농도가 높고 아스코르빈산의 첨가량이 적은 경우 생성된 Pd 침전물은 평형에 도달하면서 재용해 현상이 나타났다. 생성된 Pd 침전물은 모의용액의 성분계와 관계없이 Pd금속 결정으로 형성되었으며, $1.0{\mu}m$ 이하의 입자가 응집된 형태로 나타났다.

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Study on the Separation of MAs from HLLW and Their Extraction Behavior Using New Extractants of Amido Podand

  • An, Ye-Guo;Luo, Fang-Xiang;Zhu, Zhi-Xuan;Zhang, Xiang-Ye;Zhu, Wen-Bin
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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    • pp.245-256
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    • 2004
  • The extraction of three kinds of amido podands, N,N,N'N'-tetrabutyl-3-oxa-pentanedi- amide (TBDGA), N,N,N'N'-tetra-isobutyl-3-oxa-pentanediamide(TiBDGA) and N,N,N'N'-tetra- butyl-3,6-dioxa-oct-anediam- ide(TBDOODA) on U(VI),Pu(IV), Am(III), Eu(III) and other metal ions is studied in nitric acid solutions. 40%octanol-kerosene is chosen as diluents to eliminate third phase and emulsion. TBDGA and TiBDGA show extraction selectivity to An(III) and Ln(III) much higher than to U(VI) and Pu(IV). Fe, Ru and Mo is poorly extracted by the three kinds of amid podands in 2~3mol/L $HNO_3$ solutions. Aiming to eliminate interface crude when using simulated HLLW solution in the system of 0.2mol/L TBDGA/Octanol+kerosene, acetohydroxyamic acid was adapted. Distribution ratio of zirconium was decreased when adding acetohydroxyamic acid in aqueous solution, and interface crude disappeared as mixing extractant with HLLW. The counter-current extraction test is carried out in a set of miniature mixer-settler, with 0.2mol/L TBDGA/ 40% octanol-kerosene as extractant to separate U(VI), Pu(IV), Am(III) and Eu(III) from simulated high level liquid waste(HLLW) solution. In battery A, lanthanides and actinides are coextracted into organic phase with the recovery of 99.98% for U(Ⅵ), >99.99% for Pu(IV), and >99.99% for Am(III) and Eu(III) respectively. In battery R1, 99.99% U, 86.2% Pu and a part of Am or Eu are stripped into aqueous phase by 0.2mol/L acetohydroxyamic acid (AHA) in 0.01mol/L $HNO_3$ solution. In battery $R_2$, Am, Eu and remained Pu are completely back-extracted by 0.2mol/L AHA. This separation process contains no salt reagent, and it is not necessary to dilute HLLW feed.

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A STUDY ON ADSORPTION AND DESORPTION BEHAVIORS OF 14C FROM A MIXED BED RESIN

  • Park, Seung-Chul;Cho, Hang-Rae;Lee, Ji-Hoon;Yang, Ho-Yeon;Yang, O-Bong
    • Nuclear Engineering and Technology
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    • 제46권6호
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    • pp.847-856
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    • 2014
  • Spent resin waste containing a high concentration of $^{14}C$ radionuclide cannot be disposed of directly. A fundamental study on selective $^{14}C$ stripping, especially from the IRN-150 mixed bed resin, was carried out. In single ion-exchange equilibrium isotherm experiments, the ion adsorption capacity of the fresh resin for non-radioactive $HCO_3{^-}$ ion, as the chemical form of $^{14}C$, was evaluated as 11mg-C/g-resin. Adsorption affinity of anions to the resin was derived in order of $NO_3{^-}$ > $HCO_3{^-}{\geq}H_2PO_4{^-}$. Thus the competitive adsorption affinity of $NO_3{^-}$ ion in binary systems appeared far higher than that of $HCO_3{^-}$ or $H_2PO_4{^-}$, and the selective desorption of $HCO_3{^-}$ from the resin was very effective. On one hand, the affinity of $Co^{2+}$ and $Cs^+$ for the resin remained relatively higher than that of other cations in the same stripping solution. Desorption of $Cs^+$ was minimized when the summation of the metal ions in the spent resin and the other cations in solution was near saturation and the pH value was maintained above 4.5. Among the various solutions tested, from the view-point of the simple second waste process, $NH_4H_2PO_4$ solution was preferable for the stripping of $^{14}C$ from the spent resin.

COMPARISON BETWEEN EXPERIMENTALLY MEASURED AND THERMODYNAMICALLY CALCULATED SOLUBILITIES OF UO2 AND THO2 IN KURT GROUND WATER

  • Kim, Seung-Soo;Baik, Min-Hoon;Kang, Kwang-Cheol;Choi, Jong-Won
    • Nuclear Engineering and Technology
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    • 제41권6호
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    • pp.867-874
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    • 2009
  • Solubility of a radionuclide is important for defining the release source term of a radioactive waste in the safety and performance assessments of a radioactive waste repository. When the pH and redox potential of the KURT groundwater were changed by an electrical method, the concentrations of uranium and thorium released from $UO_2$(cr) and $ThO_2$(cr) at alkali pH(8.1 ${\sim}$ 11.4) and reducing potential (Eh < -0.2 V) conditions were less than $10^{-7}mole/L$. Unexpectedly, the concentration of tetravalent thorium is slightly higher than that of uranium at pH = 8.1 and Eh= -0.2 V conditions, and this difference may be due to the formation of hydroxide-carbonate complex ions. When $UO_2$(s) and $UO_2$(am, hyd.), and $ThO_2$(s) and $Th(OH)_4(am)$ were assumed as solubility limiting solid phases, the concentrations of uranium and thorium in the KURT groundwater calculated by the PHREEQC code were comparable to the experimental results. The dominating aqueous species of uranium and thorium were presumed as $UO_2(CO_3)_3^{4-}$ and $Th(OH)_3CO_3^-$ at pH = 8.1 ${\sim}$ 9.8, and $UO_2(OH)_3^-$ and $Th(OH)_4(aq)$ at pH = 11.4.