• Journal of Radiation Protection and Research
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• v.39 no.2
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• pp.96-102
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• 2014

Urine bioassay has been widely used for internal dosimetry due to simple process of sampling and measurement. In this paper, we participated in the NRIP (NIST Radiochemistry Intercomparison Program) hosted by US NIST to carry out a reliable performance test of urine bioassay and introduced the measurement method and results of NRIP-2013. In customary exercise with 60 days of reporting time, bioassay results of 12 radionuclides in the synthetic urine samples were acceptable based on the performance criteria of ANSI N13.30. In emergency preparedness exercise with 8 hours of reporting time, bioassay results of 9 radionuclides showed that differences ranged from -35% to 45%. However, we concluded that urine bioassay applied for emergency preparedness exercise would be applicable for rapid screening and estimation of internal exposure within a difference of ${\pm}45%$ in the event of radiological accidents.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.401.1-401
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• 2001

• Journal of Korean Society for Atmospheric Environment
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• v.3 no.1
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• pp.27-33
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• 1987

The environment and biological studies of tritium have been carried out in the advanced countries since the mid 1950's. In the case of a potential tritium exposure, the usual procedure is trifium bioassay (as HTO) in human urine in order to determine the amount of tritium deposited in the body called tritium body burden. The maximum permissible body burden(MPBB) of tritium in total body is about $30{\mu}Ci/{\ell}$ for body tissue. In the bioassay, the most common investigation level for detection of tritium in urine is 1/10th of MPBB. For this bioassay project, the first priority is given to obtaining a quench correction curve. This consideration is necessary because of the variability in color of human urine specimens. Quenching effect in this case mainly is caused by the absorption of scintillation light flashes by the urine sample. By the least squares method on the statistical basis, an estimated formula for quench correction curve was determined to be Y = 0.771 + 1.836 ${\tmes}10^{-4}$X, where the efficiency(Y) was ranged from about 12% to 31% in the liquid scientillation counting. In this paper, a brief theory concerning the biological half-life of tritium and the retention formula to apply to systematically distributed tritium are described.

• Biomolecules & Therapeutics
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• v.5 no.2
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• pp.179-186
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• 1997

The pharmacokinetics and tissue distribution of DWP20373, a novel fluoroquinolone, were examined in rats and beagle dogs after a single intravenous and oral administration. Analysis of DWP20373 in plasma, tissue, and urine was performed by both HPLC and microbiological assay. The plasma drug concentration declined biexponentially both rats and beagle dogs. In the rats, the terminal drug elimination half-life (t$_{1}$2$\beta$/) was 64 min (IV) and 57 min (PO) by bioassay, and 76 min (IV) and 77 min (PO) by HPLC. Whereas in beagle dogs, t$_{1}$2$\beta$/ was 196 min (IV) and 350 min (PO). The volume of distribution at steady-state (Vd$_{ss}$ ) was 811 ml/kg (bioassay) and 2061 ml/kg (HPLC) in rats, and 2738 ml/kg (bioassay) in beagle dogs. The total body clearance (Cl$_{t}$) of DWP20373 was 10 ml/min/kg (bioassay) and 7 ml/min/kg (HPLC) in rats, and 11 m1/min/kg (bioassay) in beagle dogs. The extent of bioavailability after oral administration was 49% (bioassay) and 67% (HPLC) in rats, and 84% (bioassay) in beagle dogs. The 24-h urinary recovery, measured by bioassay, was 2.7% after oral dosing and 5.5% after intravenous dosing in rats. Serum protein binding ratio determined at 27g/ml was 78%. This drug was also distributed in tissues in the decreasing order of liver, kidney, spleen, lung, heart, and muscle determined at 30 min after oral administration.on.

• Proceedings of the Korean Society of Toxicology Conference
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• 2005.05a
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• pp.176-176
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• 2005

• Microbiology and Biotechnology Letters
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• v.24 no.4
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• pp.472-477
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• 1996

Natural human epidermal growth factor (nhEGF) was purified from pregnant human urine by benzoic acid adsorption, DEAE-Sepharose ion exchange, and immunoaffinity chromatography. The purified nhEGF was further separated into four fractions using Bondapak C$_{18}$ HPLC system. Following characterization by Western blot analysis and double immu- nodiffusion, we found that each fraction corresponds to four derivatives of the nhEGF. For biological analysis of nhEGF, we optimized the labeling time and serum concentration for the incorporatioin of 5-bromo-2'-deoxy uridine (BrdU), a non-radioactive alternative for [$^{3}$H]-thymidine uptake, into NIH 3T3 cells. The DNA synthesis of NIH 3T3 cells was gradually increased at the nhEGF concentrations between 0.1 - 10 ng/ml in the Dulbecco's Modified Eagles Medium (DMEM) containing 0.2% Fetal calf serum (FCS). When we assayed the biological activity of four fractions, the activity of the second fraction was superior to that of the others. Based on the results from the HPLC analysis spiked with recombinant human epidermal growth factor (rhEGF) and amino acid sequencing, we concluded that the second fraction was nhEGF and the other three fractions were the derivatives of nhEGF. In addition, the proportion of nhEGF was approximately 46% is compared with that of the other three derivatives.

• Biomolecules & Therapeutics
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• v.5 no.3
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• pp.284-291
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• 1997

The pharmacokinetics and tissue distribution of DWP20367 (1-cyclopropyl-6-fluoro-8-chloro-7-(2, 7-diazabicyclo[3,3,0]tract-4-ene-7-yl)-1,4-dihydro-4-oxoquinoline-3-carboxylic acid), a novel fluoroquinolone, were examined in rats and beagle dogs after a single intravenous and oral administration. Analysis of DWP20367 in plasma, tissue, and urine was determined by both HPLC and microbiological assay (bioassay). The plasma concentration-time curves of the drug in rats and beagle dogs were biexponentially declined. The terminal half-life (t$_{1}$2$\beta$/) of the drug in rats was about 60.1 $\pm$7.3 min (i.v.) and 61.3 $\pm$ 12.4 min (p.o.) in bioassay, and 86.3 $\pm$19.8 min (i.v.) and 50.9$\pm$ 14.9 min (p.o.) in HPLC. In beagle dogs, half-life of the drug determined by bioassay was about 121.8$\pm$6.2 min (i.v.) and 111.0$\pm$7.6 min (p.o.). The volume of distribution at steady-state (Vd$_{ss}$ ) was 243.8$\pm$74.1 ml/kg (bioassay) and 339.2$\pm$84.3 ml/kg (HPLC) in rats, and 1587.5 $\pm$536.9 ml/kg (bioassay) in beagle dogs. The total body clearance (Cl$_{t}$) of DWP20367 was 3.4 $\pm$ 0.4 ml/min/kg (bioassay) and 2.4$\pm$0.4 ml/min/kg (HPLC) in rats, and 12.3$\pm$ 1.0 ml/min/kg (bioassay) in beagle dogs, respectively. The extent of bioavailability after oral administration was 89.1%(bioassay) and 79.9% (HPLC) in rats, and 78.7% (bioassay) in beagle dogs. Urinary recovery (24-h) assayed by bioassay was 0.7% (p.o.) and 1.2% (i.v.) in rats, and 0.8% (p.o.) and 1.0% (i.v.) in beagle dogs. In rats, 24-h fecal recovery determined by bioassay was 11.2% (p.o.) and 0.1% (i.v.). Rat and human serum protein binding ratios at 2$\mu$g/ml were about 90~91%. This drug determined by bioassay was also distributed by the order of liver, kidney, lung, heart, spleen and muscle 30 min after oral administration.on.

• YAKHAK HOEJI
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• v.39 no.3
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• pp.223-230
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• 1995

The phannacokinetics and tissue distribution of DWQ-013, a new quinolone, were examined in rats and mice following a single intravenous and oral administration. DWQ-013 in plasma and urine was determined by both HPLC and microbiological assay. The plasma concentration of the drug declined biexponentially. The terminal half life of the drug was 11.11$\pm$0.14 hour after intravenous dosing. The volume of distribution at terminal elimination phase(Vd$_\beta$) and total clearance of the drug were 1.29$\pm$0.15 l/kg and 0.78$\pm$0.09 l/h/kg. The bioavailability of DWQ-013 after oral administration was 56.0% (HPLC) and 77.2%(bioassay), respectively. Twelve-hour urinary recovery of drug was measured by HPLC and bioassay to 0.035$\pm$0009% and 4.71$\pm$066% after oral dosing, to 0.055$\pm$0.014% and 7.65$\pm$1.53% after intravenous dosing, which may indicate the presence of biologically active metabolites. Binding of the drug to plasma proteins ranged from 97%~99% at various concentrations. The drug was highly distributed in order of liver, kidney and lung after 1.5 hours in mice.

• Journal of Radiation Protection and Research
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• v.31 no.3
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• pp.135-140
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• 2006

Intakes of radionuclides through both inhalation and ingestion pathways may occur particularly in an incident involving unsealed radionuclides. If one assume only one intake path in this case, which is usual in routine monitoring, a significant error in the evaluated committed effective dose($E_{50}$) may result. In order to demonstrate the potential errors, variations of the resulting committed effective doses were analyzed for different fractions of the inhaled activities to the total intake of $^{241}Am$. Simulated bioassav measurements for the lungs, urine and feces were generated based on the biokinetic model and data of the radionuclide, 5 ${\mu}m$ AMAD and absorption type M for inhalation, for various inhalation fractions. The potential errors in $E_{50}$ due to the assumption of one intake path were in the range from -100% to as large as +34,000% when the bioassays were made 3 days after the intakes. Larger errors are expected when only the feces assay is applied while inhalation intake exists. A strategy which employs two types of bioassay was proposed to reduce the error caused by a misjudgement of the intake path.

• Journal of Radiation Protection and Research
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• v.38 no.2
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• pp.52-59
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• 2013

The internal contamination screening method using gross beta measurement was performed for radioisotope workers. 24 h and spot urine samples from workers of medical isotope production facilities were collected and measured. Most of the results were similar with the background level of gross beta activity except for a specific worker. Gross beta activity was slightly increased in several hours after finishing work. And the environmental factor of production facilities causing internal contamination were estimated based on screening results. The additional detailed internal dose assessment must be followed after the screening for protection of workers. Moreover, a procedure was established to apply a simple internal contamination assessment for radiation workers.