• 제목/요약/키워드: Waste solubility

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A Study About Radionuclides Migration Behavior in Terms of Solubility at Gyeongju Low- and Intermediate-Level Radioactive Waste (LILW) Repository

  • Park, Sang June;Byon, Jihyang;Lee, Jun-Yeop;Ahn, Seokyoung
    • 방사성폐기물학회지
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    • 제19권1호
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    • pp.113-121
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    • 2021
  • A safety assessment of radioactive waste repositories is a mandatory requirement process because there are possible radiological hazards owing to radionuclide migration from radioactive waste to the biosphere. For a reliable safety assessment, it is important to establish a parameter database that reflects the site-specific characteristics of the disposal facility and repository site. From this perspective, solubility, a major geochemical parameter, has been chosen as an important parameter for modeling the migration behavior of radionuclides. The solubilities were derived for Am, Ni, Tc, and U, which were major radionuclides in this study, and on-site groundwater data reflecting the operational conditions of the Gyeongju low and intermediate level radioactive waste (LILW) repository were applied to reflect the site-specific characteristics. The radiation dose was derived by applying the solubility and radionuclide inventory data to the RESRAD-OFFSITE code, and sensitivity analysis of the dose according to the solubility variation was performed. As a result, owing to the low amount of radionuclide inventory, the dose variation was insignificant. The derived solubility can be used as the main input data for the safety assessment of the Gyeongju LILW repository in the future.

파이로그린공정 희토류폐기물 유리화 타당성 연구 (Feasibility Study on Vitrification for Rare Earth Wastes of PyroGreen Process)

  • 김천우;이병관
    • 방사성폐기물학회지
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    • 제11권1호
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    • pp.1-9
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    • 2013
  • 파이로그린공정의 염폐기물처리과정에서 발생되는 주요 산화물 형태의 폐기물에는 희토류폐기물이 있으며 주요 구성 핵종은 Y, La, Ce, Pr, Nd, Sm, Eu, Gd 등 8종이다. 최종적인 희토류폐기물의 형태는 산화물 형태로 발생된다. 본 연구에서는 붕규산 유리계 내에서 희토류 산화물의 유리화 타당성을 평가 하기 위하여 6종의 유리조성을 개발하였다. 희토류 8핵종 혼합에 대한 solubility는 $1,200^{\circ}C$에서 25wt% 미만, $1,300^{\circ}C$에서 30wt% 미만 waste loading으로 온도 상승에 따라 증가하는 것으로 나타났으며 liquidus temperature는 균질한 유리가 형성된 20wt% waste loading에서 $950^{\circ}C$ 이하로 평가되었다. 희토류 산화물의 유리매질 내 solubility 이상에서는 희토류-oxide-silicate 결정이 생성된 유리세라믹을 이차상으로 형성하였으며 20~25wt% waste loading의 표면균질성이 양호한 유리는 용융온도 $1,200{\sim}1,300^{\circ}C$ 범위에서 점도 100 poise 이하, 전기전도도 1 S/cm 이상으로 유도가열식 저온용융로설비에서의 운전 용이성이 매우 양호한 것으로 평가되었다. 개발된 유리조성에 대한 기타 물리 화학적 특성 평가를 위한 실험들이 향후 수행될 예정이다.

Solubility of Mixed Lanthanide Hydroxide and Oxide Solid Solutions

  • Moniruzzaman, Mohammad;Kobayashi, Taishi;Sasaki, Takayuki
    • 방사성폐기물학회지
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    • 제19권3호
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    • pp.353-366
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    • 2021
  • The solubilities of different multicomponent lanthanide oxide (Ln2O3) solid solutions including binary (Ln1 and Ln2 = La, Nd, Eu, or Tm), ternary (Ln1, Ln2, and Ln3 = La, Nd, Eu, or Tm), and higher systems (Ln = La, Ce, Pr, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, and Lu) were studied after aging for four weeks at 60℃. Our recent study revealed that the phase transformations in binary ((La, Nd) and (La, Eu)) and ternary (La, Nd, Eu) systems are responsible for the formation of (La, Nd)(OH)3, (La, Eu)(OH)3, and (La, Nd, Eu)(OH)3 solid solutions, respectively. The variations in the mole fractions of La3+, Nd3+, and Eu3+ in the sample solutions of these hydroxide solid solutions indicated that a thermodynamic equilibrium might account for the apparent La, Nd, and Eu solubilities. Conversely, the binary and ternary systems containing Tm2O3 as the heavy lanthanide oxide retained the oxide-based solid solutions, and their solubility behaviors were dominated by their congruent dissolutions. In the higher multicomponent system, the X-ray diffraction patterns of the solid phases, before and after contact with the aqueous phase indicated the formation of a stable oxide solid solution and their solubility behavior was explained by its congruent dissolution.

Evaluation of Americium Solubility in Synthesized Groundwater: Geochemical Modeling and Experimental Study at Over-Saturation Conditions

  • Hee-Kyung Kim;Hye-Ryun Cho
    • 방사성폐기물학회지
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    • 제20권4호
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    • pp.399-410
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    • 2022
  • The solubility and species distribution of radionuclides in groundwater are essential data for the safety assessment of deep underground spent nuclear fuel (SNF) disposal systems. Americium is a major radionuclide responsible for the long-term radiotoxicity of SNF. In this study, the solubility of americium compounds was evaluated in synthetic groundwater (SynDB3), simulating groundwater from the DB3 site of the KAERI Underground Research Tunnel. Geochemical modeling was performed using the ThermoChimie_11a thermochemical database. Concentration of dissolved Am(III) in Syn-DB3 in the pH range of 6.4-10.5 was experimentally measured under over-saturation conditions by liquid scintillation counting over 70 d. The absorption spectra recorded for the same period suggest that Am(III) colloidal particles formed initially followed by rapid precipitation within 2 d. In the pH range of 7.5-10.5, the concentration of dissolved Am(III) converged to approximately 2×10-7 M over 70 d, which is comparable to that of the amorphous AmCO3OH(am) according to the modeling results. As the samples were aged for 70 d, a slow equilibrium process occurred between the solid and solution phases. There was no indication of transformation of the amorphous phase into the crystalline phase during the observation period.

Preliminary Study on the Regeneration of Spent Electro-decontamination Solution Using Phosphoric Acid and Oxalic Acid

  • Naznin, Marufa;Septian, Ardie;Shin, Won Sik
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2015년도 추계학술논문요약집
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    • pp.465-466
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    • 2015
  • In this study, different amount of (fe(0)) were dissolve into different strength of phosphoric ($H_3PO_4$) acid and the optimum solubility was observed at 0.89M Fe(0) into 4M of $H_3PO_4$ acid. Different concentration of oxalic acid was added to determine the optimum precipitated condition. The dissolution kinetics of Fe(0) into $H_3PO_4$ acid was investigated at $40-50^{\circ}C$. The optimum Fe-oxalate precipitate was dried and thermal decomposition using DSC-TG was conducted. Approximately 52 wt(%) of oxalic acid was removed at $300^{\circ}C$. Iron oxides such as magnetite and hematite that may be formed on the surface of nuclear waste were also dissolved into the $H_3PO_4$ acid and the optimum solubility for magnetite is 0.005M while that for hematite is 0.02M in 8M $H_3PO_4$ acid, respectively.

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고체 촉매를 이용한 대두유와 폐식용유의 에스테르화 (Esterification of the Soybean Oil and Waste Vegetable Oil by Solid Catalysts)

  • 신용섭
    • 한국환경과학회지
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    • 제13권1호
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    • pp.79-87
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    • 2004
  • Esterification of soybean oil with methanol was investigated. First of all, liquid-liquid equilibriums for systems of soybean oil and methanol were measured at temperatures ranging from 40 to 65$^{\circ}C$. Profiles of conversion of soybean oil with time were determined from the glycerine content in reaction mixtures for the different kinds of catalysts, such as NaOH, CaO, Ca(OH)$_2$, MgO, Mg(OH)$_2$, and Ba(OH)$_2$. The effects of dose of catalyst, cosolvent and reaction temperature on final conversion were examined. Esterification of waste vegetable oil with methanol was investigated and compared to the case of soybean oil. Solubility of methanol in soybean oil was substantially greater than that of soybean oil in methanol. When the esterification reaction of soybean oil was catalyzed by solid catalyst, final conversion was strongly dependent on the alkalinity of the solid catalyst, and increased with the alkalinity of the metal. Hydroxides from the alkali metals were more effective than oxides. When Ca(OH)$_2$ was used for the esterification catalyst, maximum value of final conversion was measured at dose of 4%. When CHCl$_3$ as a cosolvent, was added into the reaction mixture of soybean oil which catalyzed by Ba(OH)$_2$, maximum value of final conversion was appeared at dose of 3%. When waste vegetable oil was catalyzed by NaOH and solid catalysts, high final conversion, over 90%, and fast reaction rate were obtained.