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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
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Journal of Radiation Protection and Research
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Journal DOI :
Korean Association for Radiation Protection
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Volume & Issues
Volume 15, Issue 2 - Dec 1990
Volume 15, Issue 1 - Jun 1990
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Adenosine Triphosphatase Activity in Fisher Rats by Uranyl Nitrate
Lee, Kee-Ho ; Lee, Je-Ho ; Lee, Soo-Yong ; Park, Sang-Yoon ; Lee, Seung-Hoon ; Yun, Taik-Koo ; Ryu, Young-Wun ; Lim, In-Kyoung ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 1~6
An attempt was made to test the possibility of a major role for the
adenosine triphosphatase (ATPase)system in the diuresis induced by uranyl nitrate(UN). Fisher 344 rats were intravenously injected with UN(5 mg/kg, 15 mg/kg and 30 mg/kg). Urinary excretion of
significantly increased in 24 h exposure on the UN and then decreased below the normal level 3 days after the treatment.
ATPase activity of kidney was significantly inhibited in high dosages of UN 15mg/kg and UN 30 mg/kg 3-5 days after injection. And then the recovery of the enzyme activity was observed within 5-10 days after injection, at which the regeneration of the tubular cells occurred.
Sorption of Radioactive Cobalt and Ruthenium on Soil Minerals
Lee, Byung-Hun ; Hands, J.D. ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 7~16
The sorption of radioactive cobalt and ruthenium on alumina, silica gel, zeolite 3A, kaolin and Na-bentonite has been studied as a function of pH. nuclide concentration and ionic strength. Retardation factor for cobalt and ruthenium on soil minerals was determined through porosity measurement. Hydrolysed species, cobalt and ruthenium interact with solid surfaces by physical adsorption processes. Freundlich sorption isotherms for cobalt and ruthenium are effectively linear. The sorption decreases with increasing ionic strength for cobalt and ruthenium. The effect of increasing porosity on the retardation factor countered the effect of a significant increase in the distribution coefficient.
Neutron Activation Analysis of Cadmium Deposition in Hair and Animal Tissues
Ryu, Yong-Wun ; Lee, Kee-Ho ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 17~25
Rats were ingested in drinking water 600mg/L of cadmium chloride solution during 3 months, then the distribution of Cd in major organs and hair were determined by neutron activation analysis. The results were as followings. 1. After administration for 24 hours using
as tracer, the distribution of blood was 0.03%, kidney 2.99% and liver 3.50% to determine with whole body counter. 2. Cd metal was rapidly excreted with kidney through blood and their accumulation appeared in liver and hair. 3. The comparative data to determine using neutron activation analysis. the content of cadmium of major organs in rats ingested of
during 3 month were shown to increase significantly both hair and liver. Above facts, hair samples were able to use as the diagnostic index to evaluate the accumulation of cadmium in liver.
Protective Effects of Chemical Drugs on the Course of Uranium-induced Acute Renal Failure
Kim, Tae-Hwan ; Chung, In-Yong ; Kim, Sung-Ho ; Kim, Kyeng-Jung ; Bang, Hyo-Chang ; Yoo, Seong-Yul ; Chin, Soo-Yil ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 27~39
Appreciable radiation exposures certainly were occurred in the reactor burn-up, the nuelear fall-out and the surroundings of nuclear installations with radioactive effluents. Therefore, radioactive nuclides is not only potentially hazardous to workers of nuclear power plants and related industrials, but also the wokers who handle radioactive nuclides in biochemical research and nuclear medicine diagnostics. And in the case of occurring the nuclear accidents, the early medical treatment of radiation injury should be necessary but little is established medical procedures to decontaminate the victims of internal contamination of radioactive nuclides in korea. Accordingly, to achieve the basic data for protective roles and medical treatment of radiation injury, the present studies were carrid out to evaluate the decontamination of uranium by the chemical drugs. The results observed were summarized as follows: 1. The combined treatmet group of sodium bicarbonate and saline with uranyl nitrate injection simultaneously and the dithiothreitol group that was administered 30 minutes after uranyl nitrate injection were increased significantly in the change of body weight than uranyl nitrate-only group (P<0.005). 2. All the experimental groups were increased the fluid intake and urine volume on the uranyl nitrate-induced acute renal failure. but the combined treatment group of sodium bicarbonate and saline with uranyl nitrate injection simultaneously and the dithiothreitol group that was administered 30 minutes after uranyl nitrate injection have the higher increment of fluid intake and urine volume (P<0.05). 3. When sodium bicarbonate and saline was treated with uranyl nitrate injection simultaneously. and dithiothreitol was administered 30 minutes after uranyl nitrate injection. there was significantly reduced in BUN concentration (P<0.01). 4. When dithiothreitol was administered 30 minutes after uranyl nitrate injection. there was reduced more significantly on the increment of serum creatinine concentration than that observed in uranyl nitrate-only group(P<0.01). but when the combined treatment of sodium bicarbonate and saline with uranyl nitrate simultaneously, there was still. albeit much less marked. decrease in serum creatinine concentration. 5. The sodium bicarbonate and saline was treated with uranyl nitrate simultaneously and dithiothreitol was administered at 30 minutes after uranyl nitrate were excreted markedly higher urine creatinine concentration than the uranyl nitrate-only group. 6. Uranyl nitrate has been used in experimental animals to produce hydropic degeneration and swelling of proximal tubules, disappearance of microvilli and brush border or necrosis in the kidney and centrilobular necrosis, congestion, and telangiectasia of the liver. When the sodium bicarbonate and saline was treated with uranyl nitrate simultaneously, and dithiothreitol was administered. 30 minutes after uranyl nitrate, there was more marked the protective effect than uranyl nitrate-only group. Finally, if the sodium bicarbonate and saline may administered as quickly as possible each time that some risk for internal contamination, with uranium, and dithiothreitol is administered 30 minutes after uranium contamination, there ameliorates the course of uranyl nitrate-induced acute renal failure.and this effect is assocciated with prevention of uranium (heavy metal)-induced alterations in BUN, serum creatinine, urine creatinine, fluid intake, urine volume and body weight.
Effect of chelating agent and organic acid on strontium distribution in Wistar rats
Lee, Kee-Ho ; Lee, Je-Ho ; Park, Sang-Yoon ; Lee, Seung-Hoon ; Ryu, Yong-Wun ; Yun, Taik-Koo ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 41~49
was injected to the tail vein of Wistar rats and investigated its distribution and clearance in the tissues and blood. We also measured the changes in Sr binding to the blood plasma protein by administrating chelating agents and organic acids. For the blood, 60% of the Sr occurred in the plasma and 40% on the cell membrane. Fifty percent of Sr in the blood plasma was bound to plasma protein. Sr on the cell membrane seemed to be bound loosely. The binding in the lymphocyte was higher than in the erythrocyte .and granulocyte. Within one hour Sr was quickly disappeared from the blood stream, to be accumulated in the bone. Twenty four hours after the injection, Sr decreased rapidly in the organs of soft tissue, but slowly in the bone. The binding of Sr to plasma protien decreased from 57% of the control to 27-33% in the group treated with chelating agents, EDTA, EGTA and DTPA and to 19% and 40% in the groups treated with organic acids, citrate and oxalate, respectively.
An Approximation Method for the Estimation of Exposed dose due to Gamma - rays from Radioactive Materials dispersed to the Atmoshere
Kim, T.W. ; Park, C.M. ; Ro, S.G. ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 51~56
The dispersing model of radioactive plume in the atmosphere was assumed to form finite ellipseshaped volumes rather than a single plume and gamma absorbed doses from the plume were computed using the proposed model. The results obtained were compared with those computed by the Gaussian plume and the circular approximation models. The results computed by the proposed ellipse-shaped approximation model were close to those by the Gaussian plume model. and more accurate than those by the circular approximation model. The computing time for the proposed approximation model was one fortieth of that for the Gaussian plume model.
LiF(Mg, Cu, Na, Si) Thermoluminescent Dosimeters for In-phantom Dosimetry of
Kim, Hyun-Ja ; Chung, Woon-Hyuk ; Lee, Woo-Gyo ; Doh, Sih-Hong ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 57~65
Newly developed LiF(Mg, Cu, Na, Si) thermoluminescence phosphors sealed in a plastic capsules (32mm dia., 0.9mm wall thickness) were used for in-phantom dosimetry of
-irradiation. The absorbed doses in water were determined by applying the general cavity theory to the absorbed dose in TLD cavity, which was computed from exposure. The absorbed doses at various sites in the water-phantom were measured by LiF(Mg, Cu, Na, Si) TLD and compared with doses obtained by the ionization method. Both results were consistent within the experimental fluctuation(
Central axis percentage depth doses and phantom-air ratios measured by LiF(Mg. Cu, Na, Si) TLD showed good agreement with the published values [Br. J. Radiology, Suppl. 17(1983)]
A Pathway Analysis Model for Determining Acceptable Levels of Contamination of Radionuclides in Soil
Lee, Chang-Woo ; Kim, Kug-Chan ; Lee, Jeong-Ho ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 67~74
A methodology for calculating acceptable levels of contamination of radionuclides in soil for unrestricted use was described. Pathways of exposure include direct radiation from ground surfaces, ingestion of contaminated food and inhalation of resuspended radionuclides. Results calculated using site-specific data for Korean environment were discussed and compared with those estimated by other guidelines.
A Calculation of Effective Dose Equivalent from Data of Environmental Monitoring around the Karlsruhe Nuclear Research Center
Lee, Chang-Woo ; Lee, Jeong-Ho ; Wicke, A. ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 75~85
The dose calculations were carried out using environmental montoring data around Karlsruhe Nuclear Research Center(KfK). Ingestion of plant foods was the most important pathway, and the K-40 and Pb-210 natural radioisotopes in food were the most effective radiation source to man. The dose received from artificial nuclides were mostly emitted by gamma irradiation of Cs-134 and Cs-137 deposited on the ground. The effective dose equivalent in the KfK environment was far less than the dose equivalent limit recommended by ICRP.
Study on the Dosimetry and Assessment of Terrestrial Radiation Exposure
Jun, Jae-Shik ; Oh, Hi-Peel ; Ha, Chung-Woo ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 87~100
For the quantitative evaluation and assessment of radiation exposure from terrestrial component of natural environmental radiation, successive thermoluminescence dosimetry and periodical in-situ gamma ray spectrometry were carried out for a period of 24 months. LiF PTFE dise TLDs and
cylindrical NaI(Tl)scintill ation detector in association of portable multichannel analyzer (4096 ch) were used in this study. The doses measured were evaluated and assessed in terms of effective dose equivalent. As a concomitant output, the dose equivalent due to ionizing component of cosmic ray was able to be evaluated. According to the results obtained in terms of variance weighted mean, the annual effective dose equivalents of terrestrial gamma ray and cosmic ray ionizing component in Taejeon area came out to be
, respectively, which are reasonable comparably with that appeared in UNSCEAR Reportas per caput annual effective dose equivalent in 'areas of normal background radiation'.
Uncertainty and Sensitivity Analysis on A Biosphere Model
Park, Wan-Sou ; Kim, Tae-Woon ; Lee, Kun-Jai ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 101~112
For the performance assessment of the radioactive waste disposal system (repository), a biosphere model is suggested. This biosphere model is intended to calculate the annual doses to man caused by the contaminated river water for eight pathways and four radionuclides. This model can also be applied to assess the radiological effects of contaminated well water. To account for the uncertainties on the model parameter values, parameter distributions are assigned to these model parameters. Then, Monte Carlo simulation method with Latin Hypercube sampling technique is used. Also, sensitivity analysis is performed by using the Spearman rank correlation coefficients. It is found that these methods are a very useful tool to treat uncertainties and sensitivities on the model parameter values and to analyze the biosphere model. A conversion factor is proposed to calculate the annual dose rate to humans arising from a unit radionuclide concentration in river water. This conversion factor allows for the substitution of the biosphere model in a probabilistic performance assessment computer code by one single variable.
KCCH Medical Cyclotron Operation for Neutron Therapy and Isotope Production (1989) - A Technical Report -
Kim, Byung-Mun ; Kim, Young-Sear ; Bak, Joo-Shik ; Lee, Jong-Du ; Yoo, Seong-Yul ; Koh, Kyung-Hwan ;
Journal of Radiation Protection and Research, volume 15, issue 2, 1990, Pages 113~122
After four years of planning, equipment acquisition, facility construction and beam testing, the KCCH cyclotron facility was put into operation in November1986. Now the KCCH cyclotron(MC-50) has been used for four years in neutron therapy and radioisotope production. Up to December 1989, 179(1852 sessions) patient have undergone neutron therapy. Radioisotope production for nuclear medicine use was started from March 1989 after extensive work to overcome target transport, target melting, beam diagnostic and chemical processing problems. This status report introduces the cyclotron facility, and the experiences of neutron therapy and isotope production with the MC-50 cyclotron. Besides, the operation results and the general troubles of the MC-50 during 1989 are summarized. Total operation time was 1252.5 hours. Four hundred hours were used for neutron therapy of 599 treatment sessions and 832.5 hours for radioisotope production. Total amount of produced raioisotope was 1695 mCi(Ga-67 : 1478mCi, Tl-201 : 107 mCi, I-123 : 25mCi, In-111 : 85mCi). Twenty hours were used for scheduled beam testing. In 1989, 882% of the planned operation were performed on schedule and this rats is improved remarkably compared to 71.0% in 1988.