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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 16, Issue 2 - Dec 1991
Volume 16, Issue 1 - Jun 1991
Selecting the target year
Effective Dose Equivalent due to Inhalation of Indoor Radon-222 Daughters in Korea
Chang, Si-Young ; Ha, Chung-Woo ; Lee, Byoung-Hun ;
Journal of Radiation Protection and Research, volume 16, issue 1, 1991, Pages 1~13
Effective dose equivalents resulting from inhalation of indoor radon-222 daughters at 12 residential areas in Korea were assessed by a simple mathematical lung dosimetry model based on the measurements of long-term averaged radon concentrations at 340 dwellings. The long-term averaged indoor radon-222 concentrations and corresponding eqilibrium equivalent radon
measured by passive time-integrating CR-39 radon cups are in the range of
, respectively. The effective dose equvalent conversion factor for the exposure to unit
derived in this study was estimated
for a reference adult and agreed well with those recommended by the ICRP and UNSCEAR. The annual average dose equivalent to the lung
from inhalation exposure to measured
was estimated to be 20.90 mSv and resulting effective dose
was to be 1.25 mSv, which is about 50% of the natural radiation exposure of 2.40 mSv/y to the public reported by the UNSCEAR.
Measurement of Radon-222 Exhalation Rate from Building Materials by Using CR-39 Radon Cup
Chang, Si-Young ; Ha, Chung-Woo ; Lee, Byoung-Hun ;
Journal of Radiation Protection and Research, volume 16, issue 1, 1991, Pages 15~24
Radon-222 exhalation rate from several domestic building materials were experimentally measured by using radon cup method, in which a CR-39 plastic is used as a passive radon detector. The radon detection factor of CR-39 detector determined in a series of calibration experiments was
, which is consistent with those reported by other investigators. The radon exhalation rates of several building materials (brick, red brick, concrete block, granite plate, concrete floor and wall) ranges from
with the increasing order of granite plate, red brick, concrete wall, concrete block, concrete floor and brick. It showed that the CR39 radon cup can be efficiently utilized in measuring the radon-222 gas exhalation rate from building materials.
Conversion Factors for Calibration of Personnel Dosimeters
Lee, Won-Koo ; Lee, Tae-Young ; Ha, Chung-Woo ;
Journal of Radiation Protection and Research, volume 16, issue 1, 1991, Pages 25~32
MCNP code was used to calculate conversion factor H(d)ma at the depths of 0.07 and 10mm within a water phantom recommended by IAEA and within a PMMA phantom required by the US dosimeter proficiency testing programmes. The calculations were performed for an expanded parrallel beam of monoenergetic photons of perpendicular incidence on one faces of the phantom. The results can be used as conversion factor in calibrating individual dosemeters in terms of the dose equivalent quantities defined directly in the phantom.
Sr-90 Uptake by the Barley (Hordeum vulgare L. emend. Lamark) and Soil-to-Plant Transfer Coefficient
Choi, Yong-Ho ; Chung, Kyu-Hoi ; Chun, Ki-Jung ; Kim, Sam-Rang ; Lee, Jeong-Ho ;
Journal of Radiation Protection and Research, volume 16, issue 1, 1991, Pages 33~42
A pot experiment on the Sr-90 uptake by the barley from a loamy-sandy soil of pH 6.05 treated with Sr-90 and slaked lime was carried out in a green house. The rate of Sr-90 uptake at maturity was, on an average, 0.41% for a naked barley Neolssalbori and 0.23% for a covered one Olbori. Transfer coefficients of Sr-90 for the former were higher than those for the latter by about 30-60% depending on the plant parts. There were, on the whole, not significant differences in the rate and in the coefficient among Sr-90 concentration treatments. Slaked lime addition equivalent to about 94kg/10a was not effective for lessening Sr-90 uptake or diminishing Sr-90 transfer coefficient. As transfer coefficients, 1.51, 4.45, 0.35, and 1.30, on the dry weight basis, could be proposed for the stem, leaf, seed, and whole top of the barley, respectively. Growth inhibition or yield decrease due to Sr-90 uptake was not observed.
Comparison of Dose Assessment Programs; DOSE, LIMCAL and PABLM
Park, Hee-Seoung ; Cho, Won-Jin ; Han, Kyoung-Won ; Park, Hun-Hwee ;
Journal of Radiation Protection and Research, volume 16, issue 1, 1991, Pages 43~52
A comparison study is performed on dose assessment programs including DOSE, LIMCAL, and PABLM, DOSE is a program developed for preliminary safety assessments of the low- and intermediate- level radioactive waste disposal, and the others are existing programs applicable to similar calculations. The results show acceptable agreement within an order of magnitude(mrem/yr) except for C-14 and Pu-239. PABLM results higher dose for C-14 while lower value for Pu-239 in comparison with those from DOSE or LIMCAL. It is found that the discrepancy in C-14 is due to difference in transport model introduced and that in Pu-239 is from the different value of dose conversion factor to each program.
Probabilistic Safety Assessment for High Level Nuclear Waste Repository System
Kim, Taw-Woon ; Woo, Kab-Koo ; Lee, Kun-Jai ;
Journal of Radiation Protection and Research, volume 16, issue 1, 1991, Pages 53~72
An integrated model is developed in this paper for the performance assessment of high level radioactive waste repository. This integrated model consists of two simple mathematical models. One is a multiple-barrier failure model of the repository system based on constant failure rates which provides source terms to biosphere. The other is a biosphere model which has multiple pathways for radionuclides to reach to human. For the parametric uncertainty and sensitivity analysis for the risk assessment of high level radioactive waste repository, Latin hypercube sampling and rank correlation techniques are applied to this model. The former is cost-effective for large computer programs because it gives smaller error in estimating output distribution even with smaller number of runs compared to crude Monte Carlo technique. The latter is good for generating dependence structure among samples of input parameters. It is also used to find out the most sensitive, or important, parameter groups among given input parameters. The methodology of the mathematical modelling with statistical analysis will provide useful insights to the decision-making of radioactive waste repository selection and future researches related to uncertain and sensitive input parameters.