• Analytical Science and Technology
• /
• v.18 no.6
• /
• pp.469-474
• /
• 2005

This paper presents a quantitative method of sequential separation of $^{90}Sr$, $^{241}Am$ and Pu radionuclides with an anion exchange resin and a Sr-Spec resin. The Pu isotopes were purified with an anion exchange resin. The americium and strontium fractions were separated from the matrix elements with an oxalate co-precipitation method. Americium fraction was separated from the strontium fraction with iron co-precipitation method and purified from lanthanides with anion exchange resin. Strontium-90 was purified from other hindrance elements with the Sr-Spec resin after oxalate co-precipitation. The measurement of Pu and Am isotopes was carried out by an ${\alpha}$-spectrometer. Strontium-90 was measured by a liquid scintillation counter. The radiochemical procedure of $^{90}Sr$, $^{241}Am$ and Pu radionuclides investigated in this study has been validated by application to IAEA-Reference soils.

• Resources Recycling
• /
• v.31 no.5
• /
• pp.20-25
• /
• 2022

In this study, the applicability of microalgae was evaluated for eco-friendly decontamination of cesium-137 (Cs-137) and strontium-90 (Sr-90), which are radioactive nuclides contained in radioactive waste. The monolithic radioactive solution used in the experiment was manufactured at a concentration of 1.5 Bq/mL Cs-137 and 1.0 Bq/mL Sr-90 by diluting a standard radioactive solution and distilled water. This experiment used two types of microalgae, Chlorella Vulgaris was used for Sr-90 decontamination and Hematococcus pluvialis for Cs-137 decontamination. The experimental method is to put the microalgae cultured for 2 weeks into a bottle with a semi-permeable membrane, and then put the bottle in which the microalgae was put into the manufactured radioactive solution, so that the microalgae and the radioactive solution react through the semi-permeable membrane for 48 hours. For the radioactivity concentration analysis of each sample, a gamma-ray nuclide analyzer was used for Cs-137, a γ-ray isotope, and a Liquid Scintillation Count(LSC) was used f or Sr-90, a β-ray isotope. As a result of the experiment, it was confirmed that about 88.0 % of Cs-137 and about 89.7 % of Sr-90 could be decontaminated, and about 98.6 % of Sr-90 was finally able to be decontaminated by the two-stage decontamination method.

• Analytical Science and Technology
• /
• v.15 no.1
• /
• pp.20-25
• /
• 2002

An accurate and simple analytical technique for $^{89}Sr$ and $^{90}Sr$, overcoming the demerits of the conventional method, has been developed with extraction chromatography and liquid scintillation counting. The Sr fraction was separated from hindrance elements with oxalate coprecipitation or cation exchange resin and purified with Sr-Spec column. With liquid scintillation counter, $^{89}Sr$ was measured by Cerenkov radiation method, and $^{90}Sr$ was measured by spectrum unfolding method. The developed radioactive strontium separation method was validated by application to the IAEA-reference material (IAEA-375, Soil) and radioactive waste samples.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.06a
• /
• pp.248-254
• /
• 2005

This paper presents a quantitative method of sequential separation of $^{90}Sr,\;^{241}Am$ and Pu nuclides with an anion exchange resin and a Sr-Spec resin. The Pu isotopes were purified with an anion exchange resin. The americium and strontium fractions were separated from the matrix elements with an oxalate co-precipitation method. Americium fraction was separated from the strontium fraction with iron co-precipitation method and purified from lanthanides with anion exchange resin. Strontium-90 was purified from other hindrance elements with the Sr-Spec resin after oxalate co-precipitation. The measurement of Pu and Am isotopes was carried out by an ${\alpha}$-spectrometer. Strontium-90 was measured by a liquid scintillation counter. The radiochemical procedure of $^{90}Sr,\;^{241}Am$ and Pu nuclides investigated in this study has been validated by application to IAEA-Reference soils.

• Journal of Radiation Protection and Research
• /
• v.27 no.3
• /
• pp.127-146
• /
• 2002

A method of more realistically, predicting radionuclide concentrations in crop plants varying with time after a nuclear accident was established to estimate 50 years' concentrations of $^{90}Sr$ and $^{137}Cs$ in polished rice seeds and Chinese cabbage for unit dry deposition. After non-growing season accidents, concentrations of both nuclides decreased gradually with time and $^{90}Sr$ concentrations were higher than those of $^{137}Cs$ throughout the whole period. Radionuclide concentrations in the 1 st year after growing season accidents were on the whole higher than those after non-growing season accidents by factors of up to 30 for $^{90}Sr$ and up to 1,000 for $^{137}Cs$. In polished rice seeds, the 50 years-integrated concentration was higher for $^{90}Sr$ than for $^{137}Cs$ after non-growing season accidents, whereas the opposite was true after growing season accidents. In Chinese cabbage. however, it was higher for $^{90}Sr$ than for $^{137}Cs$ after both types of the accident. Generally speaking, the dominant pathway for the integrated concentration after the growing season accident was root uptake for $^{90}Sr$ and direct plant contamination for $^{137}Cs$. The effect of resuspension was negligible. Based on the predicted results. the direct]on of planning countermeasures was suggested for various accident conditions.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2009.11a
• /
• pp.131-132
• /
• 2009

시멘트 고화체 중의 Sr-90 분석을 위한 시료 전처리 방법을 실험을 통하여 확립하였다. 시멘트 고화체 중의 Sr-90 과 같은 베타방출 핵종을 분석하기 위해서는 고화체 시료를 건조, 분쇄, 산처리, Sr-90 분리 및 LSC 를 이용한 Sr-90의 방사능 측정을 해야 한다. 이를 위하여 인수 고화체 시료를 전 처리 하기 전, SRM 1887a portland cement 를 사용하여 여러 산 처리 방법을 통하여 각 원소들의 회수율을 알아보았다. SRM 시료를 통하여 얻은 조건을 참조하여 실제 고화체 시료 5g 씩 3회의 7개 시료들을 전 처리하여 ICP-AES 를 통하여 각 원소들의 회수율을 비교하였다. 또한, 전처리 후 Sr 분리에 Sr-resin (Eichrom)를 이용하기 위해서는 Sr-resin 사용 시 많은 영향을 주는 칼슘의 량을 미리 알아야 한다, 이를 위하여 시멘트 고화체 중 50% 가까이 함유되어 있는 칼슘 량을 반 정량적으로 알아내기 위한 방법을 확립하였다.

• Journal of Radiation Protection and Research
• /
• v.41 no.1
• /
• pp.49-55
• /
• 2016

Background: For the purpose of baseline data collection and enhancement of environmental monitoring the distribution studies of $^{137}Cs$ and $^{90}Sr$ in the soil of Uljin province was performed and the relation between surface soil activities and soil properties (pH, TOC and median of the surface soil) was analyzed. Materials and Methods: For 14 spots within 10 km from the NPP surface soil samples were collected and soils for depth profile were sampled for 3 spots in April 2011. Using ${\gamma}$-ray spectrometry with HPGe detector, the concentrations of $^{137}Cs$ were determined and the concentrations of $^{90}Sr$ were measured by counting ${\beta}$-activity of $^{90}Y$ (in equilibrium with $^{90}Sr$) in a gas flow proportional counter. Results and Discussion: The concentration ranges of $^{137}Cs$ and $^{90}Sr$ were $<0.479-39.6Bq{\cdot}(kg-dry)^{-1}$ (avg. $7.51Bq{\cdot}(kg-dry)^{-1}$) and $0.209-1.85Bq{\cdot}(kg-dry)^{-1}$ (avg. $0.74Bq{\cdot}(kg-dry)^{-1}$) which were similar to the reported values from other regions in Korea. The activity ratio of $^{137}Cs$ to $^{90}Sr$ in surface soils was around 9.67, which is much bigger than the initial value of 1.75 for worldwide fallouts because of faster downward movement of $^{90}Sr$ after fallout than that of $^{137}Cs$. For depth profile studies soils were collected down to 40 cm depth for the locations of Deokgu, Hujeong and Maehwa. The $^{137}Cs$ concentration distribution of the first two showed maximum values at top soils and decreased rapidly in exponential manner, while $^{90}Sr$ showed two local maximum values for soils near top and about 30 cm depth. Through linear fittings between the $^{137}Cs$ and $^{90}Sr$ concentrations of surface soil and pH, TOC and median of the surface soil, the only probable relationship obtained was between $^{137}Cs$ and TOC (determination coefficient $R^2=0.6$). Conclusion: The concentration ranges of $^{137}Cs$ and $^{90}Sr$ in Uljin were similar to the reported values from other regions in Korea. The only probable relationship obtained between activities and soil properties was between $^{137}Cs$ and TOC.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05b
• /
• pp.677-682
• /
• 1998

영광원전주변 해양에서 조사된 환경방사능 조사결과를 토대로 Cs-137과 Sr-90 방사성물질의 해수와 부유물에서 분포특성과 해양생물로의 전이.농축특성을 분석하였다. 방사성물질의 분포특성 분석은 해양에서 방사성물질의 용해성과 부유물에의 흡착성 평가뿐 아니라 방사성물질의 해양확산을 평가하는데 필수적 요소이다. 지금까지는 방사성물질의 해양확산 평가시 완전 용해성으로 가정하여 단순한 해수유동 특성만을 고려하여 평가하였으나, 흡착성 등 물리화학적 거동특성을 평가함으로써 좀더 사실적인 해양확산을 평가할 수 있다. 평가결과 Cs-137과 Sr-90의 분포특성을 나타내는 분배계수가 각각 8.1$\pm$1.4E-4, 7.4$\pm$2.3E-5 로 나타났다. 이는 두 핵종 모두 용해성이 높고 흡착성이 낮음을 보여준다. 그리고 Cs-137과 Sr-90에 비해 상대적으로 흡착성이 높게 나타나고 있다. 또 전이.농축특성 분석결과는 김에서 Cs-137과 Sr-90의 전이.농축계수가 66과 3, 서대와 병어에서는 122.5와 6, 패류에서는 Sr-90의 전이.농축계수가 6으로 나타났다. Sr-90은 전반적으로 전이.농축계수가 낮게 나타나 생물체에유입되더라도 쉽게 배출돼 축적경향이 매우 낮음을 보여준다. 반면 Cs-137은 Sr-90에 비해 상대적으로 농축특성이 높게 나타나고 있다. 향후 이를 토대로 해역의 고유 환경특성에 맞는 방사성물질의 해양중 거동특성을 고려한 해양확산평가 및 해양감시가 이뤄져야할 것이다.

• Journal of the Mineralogical Society of Korea
• /
• v.11 no.2
• /
• pp.106-116
• /
• 1998

The adsorption of Cs-137 and Sr-90 onto kaolinite in prescence of major groundwater cations (Ca2+, K+, Na+) with different concentrations was simulated by using triple-layer surface complexation model (TL-SCM). The site density (8.73 sites/nm2) of kaolinite used for TL-SCM was calculated from it's CEC and specific surface area. TL-SCM modeling results indicate that concentrations dependence on 137Cs and 90Sr adsorption onto kaolinite as a function of pH is best modeled as an outer-sphere surface reaction. This suggests that Cs+ and Sr2+ are adsorbed at the $\beta$-layer in kaolinite-water interface where the electrolytes, Nacl, KCl and CaCl2, bind. However, TL-SCM results on Sr adsorption show a discrepancy between batch data and fitting data in alkaline condition. This may be due to precipitation of SrCO3 and complexation such as SrOH+. Intrinsic reaction constants of ions obtained from model fit are as follows: Kintcs=10-2.10, KintSr=10-2.30, KintK=10-2.80, KintCa=10-3.10 and KintNa=10-3.32. The results are in the agreement with competition order among groundwater ions (K+>Ca2+>Na+) and sorption reference of nuclides (Cs-137>Sr-90) at kaolinite-water interface showed in batch test.

• Nuclear Engineering and Technology
• /
• v.14 no.3
• /
• pp.116-121
• /
• 1982

The uptake and retention of strontium-90 from seawater by the seaweed Undaria pinnatifda(sea mustard) varied depending on the plant part, exposure time, salinity, contents of stable strontium and calcium, and presence of chelating agent in the seawater. The concentration factors attained at equilibrium were in the range of 50 and it was evident that the bioaccumulation was largely due to the adsorption of the radionuclide on the surface of seaweed.