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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Journal of Radiation Protection and Research
Journal Basic Information
Journal DOI :
Korean Association for Radiation Protection
Editor in Chief :
Volume & Issues
Volume 31, Issue 4 - Dec 2006
Volume 31, Issue 3 - Sep 2006
Volume 31, Issue 2 - Jun 2006
Volume 31, Issue 1 - Mar 2006
Selecting the target year
Cancer Risk Assessment Due to Natural and Fallout Activity in Some Cities of Pakistan
Ahad A. ; Matiullah Matiullah ; Bhatti Ijaz A. ; Orfi S.D. ;
Journal of Radiation Protection and Research, volume 31, issue 1, 2006, Pages 1~7
The measured mean activities of
in the soil of Bahawalpur, Bahawalnagar and Rahimyar Khan Bistricts were 32.9, 53.6, 647.4 and 1.8 Bq
. The average absorbed dose rate calculated from these activities was 74.3 nGy
and the mean annual effective dose rate was found to be 0.46 mSv
. Absorbed doses to different body organs were derived from annual effective doses using tissue weighting factors. Radiation induced fatal cancer risks were assessed by using ICRP 60 Model. Estimations incurred 184deaths per year due to cancer.
Validation of the Long-Range Atmospheric Dispersion Model
Suh, Kyung-Suk ; Kim, Eun-Han ; Whang, Won-Tae ; Jeong, Hyo-Joon ; Han, Moon-Hee ;
Journal of Radiation Protection and Research, volume 31, issue 1, 2006, Pages 9~15
A long-range atmospheric dispersion model named LADAS has been developed to understand the characteristics of the transport and diffusion of radioactive materials released into atmosphere. The developed numerical model for validation was compared with the results of the ETEX which is the long-range field tracer experiment. As a comparative study, the calculated concentration distributions agreed well in the case of the usage of the mixing heights calculated by the Richardson number than the usage of the constant mixing heights in LADAS model. Also, the calculated concentrations agreed with the time series of the measured ones at some sampling points.
Influence of the Statistical Distribution of Bioassay Measurement Errors on the Intake Estimation
Lee, T.Y. ; Kim, J.K. ;
Journal of Radiation Protection and Research, volume 31, issue 1, 2006, Pages 17~23
The purpose of this study is to provide the guidance necessary for making a selection of error distributions by analyzing influence of statistical distribution for a type of bioassay measurement error on the intake estimation. For this purpose, intakes were estimated using maximum likelihood method for cases that error distributions are normal and lognormal, and comparisons between two distributions for the estimated intakes were made. According to the results of this study, in case that measurement results for lung retention are somewhat greater than the limit of detection it appeared that distribution types have negligible influence on the results. Whereas in case of measurement results for the daily excretion rate, the results obtained from assumption of a lognormal distribution were 10 % higher than those obtained from assumption of a normal distribution. In view of these facts, in case where uncertainty component is governed by counting statistics it is considered that distribution type have no influence on intake estimation. Whereas in case where the others are predominant, it is concluded that it is clearly desirable to estimate the intake assuming a lognormal distribution.
The Study of Radon and Uranium Distribution in the Groundwater at Regional Difference of Daejeon
Yoon, Yoon-Yeol ; Cho, Soo-Young ; Lee, Kil-Yong ; Kim, Yong-Je ;
Journal of Radiation Protection and Research, volume 31, issue 1, 2006, Pages 25~30
To know radon and uranium concentration variations in groundwater with regional difference, groundwaters were sampled at five different Daejeon area. Seventy-five samples were analyzed and forty samples were collected twice at drying and after raining season to know surface water effect. The average radon and uranium concentration of five areas are
at Daeduk-gu and
at Jung-gu. The mean concentrations of analyzed samples to know surface water effect were ranged from 0.5 to 640
for uranium and from 0.4 to 729 Bq/L for radon. The average concentration of radon and uranium after raining season were lower than those of drying season. The mean contents of radon End Uranium at drying season were
after raining season.
Study on Changes of Sperm Count and Testis Tissue in Black Mouse after Neutron Irradiation
Chun, Ki-Jung ; Seo, Won-Sook ; Son, Hwa-Young ;
Journal of Radiation Protection and Research, volume 31, issue 1, 2006, Pages 31~35
For the purpose of the biological effect in black mouse by neutron irradiation, mice were irradiated with 16 or 32 Gy neutron (flux: 1.036739E+09) by tying flat pose at BNCT facility on HANARO Reactor. And 90 days later of irradiation, physical changes of testis and testis tissue were examined. There were no weight changes but a little bit volume changes and sperm counts in the testes. Atrophy of seminiferous tubules irradiated with 32 Gy neutron is increased in number and severity and those in stage VI showed depletion of spermatogonia and pachytene spermatocytes compared to the non-irradiated control group. Testis damage of black mouse was not recovered after long time by 32 Gy neutron irradiation.
Analysis of Key Parameters for Designing the Spent Nuclear Fuel Disposal Container in Korea
Choi, Jong-Won ; Cho, Dong-Keun ; Choi, Hui-Ju ;
Journal of Radiation Protection and Research, volume 31, issue 1, 2006, Pages 37~46
For the first step to develop a reference disposal container of spent fuel to be used in a deep geological repository, this paper examined safe dimensions of the disposal container on the points of nuclear criticality and radiation safety and mechanical structural safety and provided basic information for dimensioning the container and configuration of the container components, and establishing the favorable and safe disposal conditions. When the safety factor for stress due to the external loads (hydrostatic and swelling pressure) is taken as 2.0, the safe diameter of the filler material to provide enough container strength under the assumed external loads is found to be 112cm with 13cm spacing between inner baskets in PWR container. Also the thickness of the thinner section between the fuel basket and the surface of the cast insert is determined to be 150 mm. Regarding these dimensions of the container, the PWR fuel container is sketched to accommodate 4 square assemblies or 297 CANDU fuel 297 bundles (33 circle tubes x 9 stacks). However the top and bottom parts need to be checked again through the detail radiation shielding analysis with respects to the emplacement position and handling processes of the disposal container.
A Practical and Simple Method of Self-absorption Correction for Environmental Samples
Lee, Wan-No ; Lee, Haeng-Pil ; Chung, Kun-Ho ; Cho, Young-Hyun ; Choi, Geun-Sik ; Lee, Chang-Woo ; Chung, Hyung-Wook ; Lee, Eun-Ju ; Sho, You-Sup ; Lee, Jong-Ok ;
Journal of Radiation Protection and Research, volume 31, issue 1, 2006, Pages 47~52
A self-absorption correction is important issue for the exact radioactivity determination of gamma emitting radionuclides in environmental samples which have the range of apparent density from
. In this paper, a practical and simple method without radioactive standard solutions having various densities is proposed for the self-absorption correction of environmental samples by a developed outside beaker surrounding Marinelli beaker. For the densities of 0.8, 1.0,
, the corrected efficiencies by the new method and the measured those by radioactive standard solutions of the three densities showed good agreement within 4 %.