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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
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Volume & Issues
Volume 29, Issue 4 - Dec 2004
Volume 29, Issue 3 - Sep 2004
Volume 29, Issue 2 - Jun 2004
Volume 29, Issue 1 - Mar 2004
Selecting the target year
Improvement on the Method of Estimating Radionuclide Concentrations in Agricultural Products for the Off-Site Internal Dose Calculation for Operating Nuclear Facilities
Choi, Y.H. ; Lim, K.M. ; Hwang, W.T. ; Choi, G.S. ; Choi, H.J. ; Lee, C.W. ;
Journal of Radiation Protection and Research, volume 29, issue 2, 2004, Pages 73~90
The Reg. Guide 1.109 model was reviewed against its applicability to calculating radionuclide concentrations in agricultural products for operating nuclear facilities and an improved method was proposed. The model was so modified that the radionuclides deposited since the start of operation could be considered in assessing the root uptake. Translocation factors were introduced in the equation for calculating the concentrations in edible parts due to direct plant deposition. Values specific to Korea were set up for the input parameters of the modified model. The concentrations of
in rice seeds, Chinese cabbage and radish root were calculated for various hypothetical deposition histories using the Reg. Guide 1.109 model and the modified model with parameter values in the guide and those specific to Korea put in alternately. Through comparisons among the results, it could be expected that the use of the modified model with the input of parameter values specific to Korea would result In a more resonable and realistic assessment.
A Practical Methodology for Determination of Derived Intervention Levels on Relocation Following a Nuclear Accident
Hwang, Won-Tae ; Kim, Eun-Han ; Suh, Kyung-Suk ; Jeong, Hyo-Joon ; Han, Moon-Hee ; Lee, Chang-Woo ;
Journal of Radiation Protection and Research, volume 29, issue 2, 2004, Pages 91~96
A practical methodology for the determination of derived intervention levels (DILs) on relocation following an accidental release of radionuclides was designed based on dose rate on the ground. The influence of DILs was investigated with respect to the change of parameter values, which are dependent on socio-environmental characteristics in distinction from temporary and permanent relocations. The DILs on relocation showed a distinct difference depending on effective removal half-life of radionuclides following a deposition, delay time in measurement and residential characteristics. In particular, the delay time. In measurement was an important factor in determination of DILs in the case of an assumption that dose rate on the ground declines in a power function, not in an exponential function. The DILs showed lower numerical values as longer effective half-life, longer delay time In measurement and longer exposure time.
Construction of MIRD-type Korean Adult Male Phantom and Calculation of Dose Conversion Coefficients for Photon
Park, Sang-Hyun ; Lee, Choon-Sik ; Lee, Jai-Ki ;
Journal of Radiation Protection and Research, volume 29, issue 2, 2004, Pages 97~104
MIRD-type Korean adult male phantom, 'KMIRD' was constructed to calculate Korean-specific dosimetric quantities for radiation protection consideration. The external shape of KMIRD was based on national physical standard data of Korean. KMIRD has thicket trunk than MIRD5 and arm models divided from trunk. The height and weight of the KMIRD are 171 cm and 63.8 kg. ICRP23 data were referred to constitute organs and tissues of KMIRD. However nine organs were constructed based on Korean reference data provided by Radiation Health Research Institute. In the present study, the MCNPX2.3 Monte Carlo transport code was combined with KMIRD to calculate dose conversion coefficients for photon in the energy range from 0.05 to 10 MeV. The simulated irradiation geometries are broad parallel photon beams in AP, PA, LLAT and RLAT direction. Absorbed dose conversion coefficients were compared with data calculated with MIRD5, MIRD-type phantom based on ICRP23 reference man. In some organs, the discrepancies between two phantoms amount up to nearly 30%. The effective doses conversion coefficients of KMIRD are lower than those of MIRD5. The dose discrepancies between two MIRD-type phantoms ate because of physical differences between Korean and Western, also geometric differences between two phantoms. KMIRD should be revised using the full set of Korean reference data of all organs. The developed MIRD-type Korean adult male phantom can be applied to dose assessment of internal exposure.
The Effects of the Statistical Uncertainties in Monte Carlo Photon Dose Calculation for the Radiation Therapy
Cheong, Kwang-Ho ; Suh, Tae-Suk ; Cho, Byung-Chul ;
Journal of Radiation Protection and Research, volume 29, issue 2, 2004, Pages 105~115
The Monte Carlo simulation requires very much time to obtain a result of acceptable accuracy. Therefore we should know the optimum number of history not to sacrifice time as well as the accuracy. In this study, we have investigated the effects of statistical uncertainties of the photon dose calculation. BEAMnrc and DOSXYZnrc systems were used for the Monte Carlo dose calculation and the case of mediastinum was simulated. The several dose calculation result from various number of histories had been obtained and analyzed using the criteria of isodose curve comparison, dose volume histogram comparison(DVH) and root mean-square differences(RMSD). Statistical uncertainties were observed most evidently in isodose curve comparison and RMSD while DVHs were less sensitive. The acceptable uncertainties
of the Monte Carlo photon dose calculation for the radiation therapy were estimated within total 9% error or 1% error for over than
voxels or voxels at maximum dose.
Model for Transport of Accidently Released Radionuclides onto Rice-Fields and its Comparison with Experimental Data
Keum, Dong-Kwon ; Lee, Han-Soo ; Choi, Heui-Joo ; Kang, Hee-Suk ; Lim, Kwang-Muk ; Choi, Young-Ho ; Lee, Chang-Woo ;
Journal of Radiation Protection and Research, volume 29, issue 2, 2004, Pages 117~127
A dynamic compartment model was developed to evaluate the transport of accidently released radionuclides onto rice-fields. In the model, the surface water compartment and shoot-base absorption were introduced to account for the effect of irrigation, which is essential to a rice cultivation. The soil mixing by plough and irrigation before transplanting rice was also considered, and the rate of root-uptake and shoot-base absorption were modeled in terms of the function of biomass. In order to test the validation of the model, it was applied to the analysis of some simulated
deposition experiments that were performed while cultivating rice in a greenhouse using soils sampled from rice-fields around Kori, Yonggwang and Ulchin nuclear power plants. The model prediction was generally agreed within about one order of magnitude with experimental data.
Radiological Risk Assessment for
Generator using Uncertainty Analysis
Jang, H.K. ; Kim, J.Y. ; Lee, J.K. ;
Journal of Radiation Protection and Research, volume 29, issue 2, 2004, Pages 129~139
Recently, much attentions are paid to the risk associated with increased uses of medium size radiation sources in medical and industrial fields. In this study, radiation risks to the worker and to the general public due to
generator were assessed for both normal and accident conditions. Based on the event tree technique, exposure scenarios for various situations were derived. Uncertainty analysis based on the Monte-Carlo technique was applied to the risk assessment for workers and members of the public in the vicinity of the work place. In addition, sensitivity analysis was performed on each of the five independent input parameters to identify importance of the parameters with respect to the resulting risk. Because the frequencies of normal tasks are fat higher than those of accidents, the total risk associated with normal tasks were higher than the accident risk. The annual dose due to normal tasks were
for workers and
for public, while in accident conditions
, respectively. Uncertainty range of accident risk was higher by 10 times than that of normal risk. Sensitivity analysis revealed that source strength, working distance and working time were crucial factors affecting risk. This risk analysis methodology and its results will contribute to establishment of risk-informed regulation for medium and large radioactive sources.
Calculation of Route Doses for Korean-based International Airline Routes using CARI-6 and Estimation of Aircrew Exposure
Hong, J.H. ; Kwon, J.W. ; Jung, J.H. ; Lee, J.K. ;
Journal of Radiation Protection and Research, volume 29, issue 2, 2004, Pages 141~150
Dose rate characteristics of cosmic radiation field at flight altitudes were analyzed and the route doses to the personnels on board due to cosmic-ray were calculated for Korean-based commercial international airline routes using CARI-6. Annual individual doses to aircrew and the collective effective dose of passengers were estimated by applying the calculated route doses to the flight schedules of aircrew and the air travel statistics of Korea. The result shows that the annual doses to aircrew, around 2.62 mSv, exceed the annual dose limit of public and are comparable to doses of the group of workers occupationally exposed. Therefore it is necessary to consider the frequent flyers as well as the aircrew as the occupational exposure group. The annual collective dose to 11 million Korean passengers in 2001 appeared to be 136 man-Sv. The results should be modified when the dose rates of cosmic radiation at high altitude are revised by taking into account the changes in the radiation weighting factors for protons and neutrons as given in ICRP 92.