• Journal of the Korean Chemical Society
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• v.13 no.2
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• pp.181-186
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• 1969

The concentration of Strontium-90 in liquid whole milk produced in Korea were measured during past four years. The samples of milk were purchased from dairies in Seoul. Strontium-90 was analysed radiochemically and the amount of stable calcium was also determined. Radioactivity of Yttrium-90 was counted in low background beta counter which has the background of 1.38 cpm. The concentrations of Strontium-90 in the milk are 25.1 PCi $^{90}Sr$/g.Ca in 1965, 26.8 PCi $^{90}Sr$/g. Ca in 1966, 13.7 PCi 90Sr/g.Ca in 1967 and 18.2 PCi $^{90}Sr$/g.Ca in 1968 in annual average. The concentrations of Strontium-90 in the milk of 1967 and of 1968 were decreased approximately compared with the values of 60% 1965 and 1966. From the results we can see that Strontium-90 concentrations in the milk vary roughly proportionally with the specific activity of fallout. Considering on the safety problems, the Strontium-90 levels in the milk produced in Korea were far below the maximum permissible level recommended by ICRP.

• Nuclear Engineering and Technology
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• v.15 no.2
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• pp.110-116
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• 1983

The absorption and translocation of strontium-90 by soybean plant, Glycine max, was studied by applying strontium-90 solution on the foliage or on the soil surface right after the first flowering time under greenhouse conditions. The results are summarized as follows. In the foliar application of strontium-90, only a small portion of the radioactivity was translocated to other parts of the plant and most of it remained in the applied leaves, which should cause soil contamination after falling. In the soil surface application of strontium-90, much of the radioactivity was absorbed through the root and translocated to stems and leaves by different patterns depending on the growth stage.

• The Journal of the Korean dental association
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• v.13 no.12
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• pp.1163-1169
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• 1975

• Nuclear Engineering and Technology
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• v.3 no.1
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• pp.9-13
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• 1971

The levels of strontium-90 in milk produced in Korea were determined during the past six years. Milk samples were collected from dairies and market shops in seoul area. Strontium-90 in milk was separated from calcium using fuming nitric acid and purified radiochemically. After seculear equilibrium was completed, the radioactivity of yttrium-90 was counted in a low background beta counting system. The determination of stable calcium in milk was also made by volu-metric method using 0. 1 N potassium permanganate solution. The highest value of 34.9 pCi $^{90}$ Sr/g-Ca was determined in August, 1966 and the lowest value was 7.5 pCi $^{90}$ Sr/g-Ca in August, 1967. From the result we can say that levels of strontium-90 are decreasing year after year and are far bellow the maximum permissible level recommended by International Committe on Radiation Protection.

• Journal of Environmental Health Sciences
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• v.20 no.3
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• pp.61-77
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• 1994

Sprague Dawley rats were exposed to electric fields (6,000 V, 10 kV/m, 30 min/day, 6 days per week) and injected strontium 90 (681 kbq/rat, one time) through abdominal cavity (strontium 90 and electric field complexed exposure group). In parallel, series with the electric field exposure only, strontium 90 injection only and control groups were run. Every group was consisted of 110 rats (55 male and 55 female). This animal experiment was performed from May to December in 1993. This results were conducted to investigate the effect of electric field for 11 weeks. The results are summarized as follows: 1. Ornithine decarboxylase (ODC) activity in rat's bone marrow cells: The ODC values was significantly increased in Sr$^{90}$ injection group and Sr$^{90}$ and electric field complexed exposure group as compared with that of control group (p<0.05). The ODC value was significantly decreased in electric field and Sr$^{90}$ complexed exposure group in comparison with Sr$^{90}$ injection group (p<0.05). The ODC values of electric field only exposure group was not different to that of control group (p>0.05). 2. The amount of Sr$^{90}$ accumulation in the femur, kidney and spleen:The accumulation amount of Sr$^{90}$ in the femur of Sr$^{90}$ injection group represented higher value than that of electric field and Sr$^{90}$ complexed exposure group (p<0.05). In the kidney and spleen, the difference between electric field and Sr$^{90}$ complexed exposure group and Sr$^{90}$ injection group wasn't observed. 3. The counts of white cells in blood of Sr9?injection group was decreased as compared with the value from control group and electric field and Sr$^{90}$ complexed exposure group (p<0.05). The rat's body weight, red blood cell counts and the weight data of liver, kidney and spleen did not show differences among four groups.

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

• Journal of the Korean Crystal Growth and Crystal Technology
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• v.6 no.4
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• pp.501-508
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• 1996

Strontium barium niobate powders were prepared by NaCl-KCl molten salt, and reaction process and morphology change of strontium barium niobate were investigated as a function of reaction temperature, time, and amount of molten salt. With increasing the reaction temperature and time, the reacted fraction was increased and the morphology of powder was changed from lumpy shape into meedle-like shape. With increasing the amount of molten salt, reacted fraction was increased rapidly, but the morphology of powder was changed from needle-like shape into spherical shape. Strontium barium niobate powder, over 90 % in fraction reacted, was obtained from the reaction conditions at $1000^{\circ}C$ for small flux ratio (=1) and at $650^{\circ}C$ for large flux ratio (=4).

• Journal of Soil and Groundwater Environment
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• v.20 no.2
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• pp.32-40
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• 2015

Laboratory column experiments were conducted to evaluate the feasibility of injectable apatite method for the sequestration of Sr-90 in groundwater. The columns were tested to evaluate the rate of citrate biodegradation, the amounts of apatite formed, and the treatability of strontium by the sediment and apatite. The results showed the decreases in citrate, calcium, and phosphate concentrations and the increases in alkalinity and citrate degradation products (acetate and formate) in the columns, suggesting that the citrate degradation and formation of calcium phosphate are occurring. Although the calcium and phosphate were not completely consumed within the columns, some amounts of apatite were formed and it showed an ability to treat strontium in groundwater. This study provides a fundamental understanding of reaction mechanisms for the injectable apatite sequestration method for Sr-90 removal.

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

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