• 월간낙농육우
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• v.25 no.8 s.280
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• pp.125-131
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• 2005

• KOREAN POULTRY JOURNAL
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• v.33 no.4 s.378
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• pp.130-131
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• 2001

• Proceedings of the Korean Vacuum Society Conference
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• 2005.02a
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• pp.131-131
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• 2005

• Journal of radiological science and technology
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• v.31 no.1
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• pp.41-47
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• 2008

In order to better understand the effects of absorbed radioiodine upon Korean reference adult male, a mathematical phantom representation was contrived based on composite data of the physiology of Korean reference adult male. Using this, S-values of radioiodine($^{131}I$) per each organ were calculated. The calculated S-values were compared to the existing data described in the TM-8381 report of ORNLcalculated on the basis of an ICRP-23 reference male. The results indicated that S-values were higher for the phantom based on Korean reference adult male. The results of this study illustrate that, while the bio-chemical constitution of each source and target organ of the torso are important, the relative location of the organs and characteristics of the radionuclides also exert important influences.

• The Korean Journal of Nuclear Medicine
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• v.28 no.3
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• pp.402-406
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• 1994

Pheochromocytomas are catecholamine-producing tumors of neuroectodermal origin, and may arise wherever chromaffin cells are located. They are rare but potentially lethal and amenable to surgical cure. Once a clinical diagnosis has been established, localization becomes of importance to direct surgical approach. MIBG scintigraphy is the initial localizing procedure of choice, due to its ability to screen the entire body, especially in the detection of extraadrenal and recurrent pheochromocytoma. A case of recurrent extraadrenal pheochromocytoma diagnosed by $^{131}I$-MIBG scintigraphy is presented with review of the literature.

• Journal of Radiation Protection and Research
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• v.14 no.1
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• pp.8-15
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• 1989

After administration of $^{99m}TC,\;^{67}Ga,\;^{131}I,\;^{32}P\;and\;^{238}U(UO_2(NO_2)_3{\cdot}6H_2O)$, in male rats, toxic effects were examined by determining the biological materials in blood. Dosages of radio-nuclides injected are based on the amounts routinely administered to patients, and concentrations of BUN, creatinine, SGOT, SGPT and $PGE_2$ in plasma are determinated as indices to the biochemical response. No increase of creatinine was observed after injection of $^{99m}TC$. Concentrations of BUN, SGOT and $PGE_2$ were not significantly increased in comparison with before-administration. Administration of $^{67}Ga,\;^{131}I\;and\;^{32}P$, did not significantly change BUN, SGPT and SGOT, but largely increased $PGE_2$ than control levels. Besides, $^{238}U$ Showed the most severe toxicity. From the above results, we suggest that the determination of $PGE_2$ in plasma can be used as an index in case of elvaluating the effects of radiation toxicity by nuclides used in nuclear medicine.

• Journal of Radiation Protection and Research
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• v.19 no.1
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• pp.69-80
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• 1994

The TCMI(Three-Compartment Model for iodine) computer code has been developed, which is based on the three-compartment model and the respiratory model recommended in ICRP publication 54. This code is able to evaluate the thyroid burden, dose equivalent, committed dose equivalent and urinary excretion rate as time-dependent functions from the input data: working time and the radioiodine concentration in air. Using the TCMI code, the time-dependent thyroid burdens, the thyroid doses and the urinary excretion rates were calculated for three specific exposure patterns : acute, chronic and periodic. Applicability as an internal dose evaluation method has been assessed by comparing the results with some operational experiences. Simple equations and tables are provided to be used in the evaluation of the thyroid burden and the resulting doses for given I-131 concentration in air and the working time.

• Nuclear Engineering and Technology
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• v.56 no.6
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• pp.2050-2056
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• 2024

Handling of radioisotopes may cause external and internal contamination to occupational workers while using radiation for medical purposes. This research aims to monitor the internal hazard of occupational workers who handle ¹³¹I. Two methods are used: in vivo or direct method and in vitro or indirect method. The in vivo or direct method was performed by assessing thyroid intake with a thyroid uptake monitoring machine. The in vitro or indirect method was performed by assessing urine samples with the help of a gamma-ray spectroscopy practice using a High-Purity Germanium (HPGe) Detector. In this study, fifty-nine thyroid counts and fifty-nine urine samples were collected from seven occupational workers who were in charge of ¹³¹I at the National Institute of Nuclear Medicine and Allied Sciences (NINMAS), Dhaka. The result showed that the average annual effective dose of seven workforces from thyroid counts were 0.0208 mSv/y, 0.0180 mSv/y, 0.0135 mSv/y, 0.0169 m Sv/y, 0.0072 mSv/y, 0.0181 mSv/y, 0.0164 mSv/y and in urine samples 0.0832 mSv/y, 0.0770 mSv/y, 0.0732 mSv/y, 0.0693 mSv/y, 0.0715 mSv/y, 0.0662 mSv/y, 0.0708 mSv/y.The total annual effective dose (in vivo and in vitro method) was found among seven workers in average 0.1039 mSv/y, 0.0950 mSv/y, 0.0868 mSv/y, 0.0862 mSv/y, 0.0787 mSv/y, 0.0843 mSv/y, 0.0872 mSv/y. Following the rules of the International Commission on Radiological Protection (ICRP), the annual limit of effective dose for occupational exposure is 20 mSv per year and the finding values from this research work are lesser than this safety boundary.

• The Korean Journal of Nuclear Medicine
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• v.26 no.2
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• pp.280-289
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• 1992

The 20-minute $^{99m}Tc-pertechnetate$ uptake became readily available for routine use and it replaced $^{131}I$ for thyroid imaging. However measuring thyroid uptake during a 5-minute minimizes pertechnetate uptake by the salivary glands and presence of contaminated saliva from those glands in to the pharynx and esophagus. A study was carried out to determine the suitability of the utility of a S-minute and 20-minute interval from administration of $^{99m}Tc-pertechnetate$ to imaging and uptake measurement as a replacement for the 24 hour standard originally established with $^{131}I$, and to evaluate the relationship between 5-minute $^{99m}Tc-pertechnetate$ uptake and other thyroid functions. A 5-minute and 20-minute uptake of $^{99m}Tc-pertechnetate$ were measured in 70 patients with thyroid disease at Yeungnam University Hospital from March 1, 1991 to Feb. 29, 1992. The results were as follows. 1) The 5-minute $^{99m}Tc-pertechnetate$ uptake in Graves' disease, Hashimoto's thyroiditis, simple goiter, non toxic nodular goiter, subacute thyroiditis and euthyroid were 18.2%, 14.6%, 2.8%, 3.2%, 1.2% and 1.1%, respectively. There was a significant difference between the mean of the euthyroid group and the mean of the Graves' disease. So differenciation between them can be easily made. 2) The 5 minute $^{99m}Tc-pertechnetate$ thyroid uptake was well correlated with 24 hour $^{131}I$ thyroid uptake (r=0.75, p<0.001). These data provided an equation for estimating the 24 hour uptake of iodide given the 5 minute pertechnetate uptake: Estimated 24-hour $^{131}I$ thyroid Uptake= 7.188*ln (5 minute $^{99m}Tc-pertechnetate$ uptake)+16.94 3) The 20-minute $^{99m}Tc-pertechnetate$ thyroid uptake was well correlated with 24-hour $^{131}I$ uptake (r=0.72, p<0.001) and 5-minute $^{99m}Tc-pertechnetate$ thyroid uptake (r=0.96, p<0.001). 4) In the Graves' disease, The 5-minute $^{99m}Tc-pertechnetate$ thyroid uptake was well correlated with serum $T_3-resin$ uptake (r=0.46, p<0.01), serum total $T_3$ (r=0.55, p<0.05), serum total $T_4$ (r=0.46, p<0.05). These results suggest that 5-minute ${99m}Tc-pertechnetate$ thyroid uptake has been found at least as useful as 24-hour $^{131}I$ uptake for diagnostic confirmation at our hospital, the logistical advantages of completing the diagnosis. The exam in 5-minutes led us to abandon the 24-hour study in the majority of patients, but the 24-hour $^{131}I$ uptake is still obtained in patients with planned or potential radioiodine therapy.

• The Korean Journal of Nuclear Medicine
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• v.27 no.1
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• pp.112-117
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• 1993

Background Radioiodine ($^{131}I$), a major component of nuclear fallout and a valuable therapeutic agent for thyrotoxicosis and thyroid cancer, has been regarded as a mutagen or a carcinogen without any convincing evidence. To evaluate the genotoxicity of radioiodine ($^{131}I$) we performed a micronuclei test in mice bone marrow. Materials and methods : Mice (ICR strain, $25{\sim}30 g$) were divided to 4 groups: control, group 1 (0.17 mCi/kg, usual therapeutic dose for thyrotoxicosis), group 2 (1.67 mCi/kg, usual therapeutic dose for thyroid cancer), and group 3 (16.67 mCi/kg, usual accumulated dose causing bone marrow suppression). $^{131}I$ was administered intraperitoneally. Ten mice of each group were sacrificed at days 1 and 3. Bone marrow were smeared and stained with May-Grunwald Giemsa method. One thou-sand polychromatic erythrocytes (PCE) and normochromatic erythrocytes (NCE) were counted under the light microscope, and the number of micronucleated PCEs were recorded. Results : The frequency of micronuclei in PCE (and NCE in parenthesis) in the control group was $0.25{\pm}0.07$ ($0.23{\pm}0.07$)% in day 1 and $0.24{\pm}0.07$ ($0.21{\pm}0.07$)% in day 3. Those in group 1 was $0.27{\pm}0.1$ ($0.23{\pm}0.09$)% in day 1 and $0.28{\pm}0.07$ ($0.25{\pm}0.06$)% in day 3. Micronuclei was noted in $0.29{\pm}0.08$ ($0.26{\pm}0.09$)% in day 1 and $0.31{\pm}0.05$ ($0.29{\pm}0.06$)% in day 3 in group 2, and in $0.32{\pm}0.06$ ($0.25{\pm}0.09$)% in day 1 and $0.33{\pm}0.08$ ($0.3{\pm}0.06$)% in day 3 in group 3. There was no difference in the frequency of micronuclei between each groups (p> 0.05). Conclusion : Radioiodine ($^{131}I$) did not cause any genotoxicity in mice bone marrow even at the large dose (16.67 mCi/kg).