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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 13, Issue 2 - Dec 1988
Volume 13, Issue 1 - Jun 1988
Selecting the target year
The Stopping Power and Cross-section Measurement of
-particle in Ar, He and
Lee, Jung-Hoon ; Hwang, Jae-Kwang ; Hwang, Han-Yull ; Chung, Won-Mo ; Joo, Koan-Sik ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 1~8
The energy losses of
-particle with 3 to 5.4 MeV energy were measured as a function of gas absorber thickness and
-particle energy in three light gaseous media; He, Ar, and
. The stopping powers and stopping cross-sections were determined by analyzing these data. For Ar gas, the experimental values are very well consistent with the corresponding values of Srivastava's stopping-power theory with the condition of the completely and partially stripped ion. For
and He gases, these experimental values express the inconsistencies of about
Study on The Quantification of Cosmic-Ray Component Contributed to Natural Background Radiation Exposure
Jun, Jae-Shik ; Oh, Hi-Peel ; Ha, Chung-Woo ; Oh, Heon-Jin ; Kang, In-Seon ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 9~20
In order to quantify the contribution of cosmic-ray ionizing component to the dose given by natural background radiation, a series of measurement has been carried out using LiF TLDs for about one and a half years on quarterly basis. Three different types of LiF TLDs namely, chips and PTFE based disks of
, and the same disks of
for identifying possible contribution of neutron component were used. Measurements were made by placing badge-incased TLDs in a lead castle of 10 to 15cm thick installed in a room on the third floor of a four-story building in CNU Daedeok campus for 5 cycles of 90 days. For comparison a series of spectrometric study was also performed for the energy region over 3MeV using a 3'
'NaI(Tl) scintillation detector in association with an MCA of 1024 channels, and it was found that the data obtained by the TLDs placed in the lead castle indicate 75% of the dose given by outdoor cosmic-ray component. The results obtained by the TLDs through correction for shielding loss show that the outdoor dose contribution of ionizing component of cosmic rays at this campus is
which satisfactorily agrees with that expected for our particular location of measurement.
Measurement and Analysis of X-ray Absorbed Dose in Water Phantom using TLD
Oh, Jang-Jin ; Jun, Jae-Shik ; Hah, Suck-Ho ; Kim, Wuon-Shik ; Hwang, Sun-Tae ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 21~28
Absorbed dose in water was analyzed by Burlin's general cavity theory for medium X-ray energy region (HVL : 0.29, 0.84, 1.60, 2.62mm Cu) using LiF : PTFE TL dosimeter(0.4 mm
12.5mm, hot-pressed LiF TLD-700) which was enclosed in lucite capsule. The absorbed dose rate at 5cm depth in water phantom was determined with measurement error of
. This result was compared to that of the ionization method, indirectly absolute measurement method, of which measurement error of
. The difference between these two results lies within measurement error of LiF : PTFE method. Therefore, the absorbed dose in water obtained by LiF: PTFE is reliable, and this result suggests the base to estimate dose-equivalent for medium X-rays.
Determination of Spectrum-Exposure Rate Conversion Factor for a Portable High Purity Germanium Detector
Kwak, Sang-Soo ; Park, Chong-Mook ; Ro, Seung-Gy ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 29~40
A spectrum-exposure rate conversion operator G(E) for a portable HPGe detector used for field environmental radiation survey was theoretically developed on the basis of a space distribution function of gamma flux emitted from a disk source and an areal efficiency of the detector. The radiation exposure rates measured using this G(E) and the portable HPGe. detector connected to a portable multichannel analyzer were compared with those measured by a 3'
3' NaI(Tl) scintillation detector with the reported G(E) and a pressurized ionization chamber. A comparison of the three results showed that the result obtained using the HPGe detector was lower than those determined using the NaI(Tl) detector and ionization chamber by 17% to 29%, The difference obtained is close to that reported in literature. The method developed here can be easily applicable to obtain a G(E) factor suitable to any detector for detecting the exposure rate of environmental gamma radiation, since the spectrum-exposure rate conversion operator can be calculated by a hand calculator.
Comparative Analyses of the Internal Radiation Exposures due to Food Chain Pathway Using FOOD III Code
Choi, Yong-Ho ; Chung, Kyu-Hoi ; Kim, Jin-Kyu ; Lee, Jeong-Ho ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 41~51
In order to develop a food-chain computer code suitable to the environmental conditions of Korea, the FOOD III code was partially modified. The excution results for Korean male-adult were compared to those from the Canadian version of FOOD III to deduce a more realistic approach in dose assessment. The amounts of Mn-54, Co-58, Co-60, I-131 and I-132 released from Kori unit 1 in1984 were used as the source terms for the sample calculation. The maximum atmospheric dispersion factor(X/Q) value on the site boundary was applied. Through the code modification, organ doses decreased by about
and the effective committed dose equivalent by about 40% to be
which is 0.16% of the ICRP limit,
Comparison of the Ion-exchange Method and Evaporation Method for the Detection of Radioactivity in Water
Ji, Pyung-Gook ; Park, Chong-Mook ; Ro, Seung-Gy ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 52~56
An ion-exchange method for the detection of radioactivity in water using ion-exchange resin in concentrating radioactive nuclides was compared with an evaporation method. The loss of the radioactive materials in the sample treated by the ion-exchange method was less by about 20% than that by the evaporation method. In addition, the evaporation method needed about 20 hours for evaporating one liter of the sample at
, while the ion-exchange method spent 6 hours to adsorb and adsorb the same amount of the sample on the resin. Consequently, the ion-exchange method is more effective than the evaporation method for the treatment of the radioactively contaminated water and is especially suitable for detecting the low-level radioactivity in water.
Measurement of Radon Concentration in the near-surface Soil Gas by CR-39 Detectors
Kang, D.W. ; Kim, H.G. ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 57~66
A series of experiments is performed to measure radon concentration in the near-surface soil gas at the four locations (Cheju-Si, Seoguipo-Si, Taejeong-eup, Seongsan-eup) in Cheju Island, using CR-39 detectors placed inside radon cups. Two types of radon cups are installed in shallow holes of about 15 cm in diameter and 50cm in depth. The optimum etching conditions, i.e., the concentration of NaOH solution, etchant temperature and etching time, are found to be 625N,
and 5.5 hours for CR-39 detectors. A typical conversion factor of radon cup is calculated as
. Average radon concentrations over 30 days measured in Cheju Island from May 1, 1987 to April 23, 1988 are
for open radon cups and
for closed radon cups.
A Rapid Dose Assessment and Display System Applicable to PWR Accident
Moon, Kwang-Nam ; Yook, Chong-Chul ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 67~77
The necessity of developing a rapid dose assessment system has been emphasized for an effective emergency response of mitigation of off-site radiological consequences. A microcomputer program based on a rapid dose assessment model of the off-site radiological consequences is developed for various accdident sinarios for the Nuclear Power Plants in Korea. This model, which is consists of the user answering-question input format as a menu driven method and the output format of table and graphic types, is helpful to decision-making on Emergency Preparedness by being more rapidly able to implement the off-site dose assessment and to interpret the result.
Assessment of Relative Importance to the Early Effect of Released Radionuclides During Nuclear Power Plant Accident
Moon, Kwang-Nam ; Yook, Chong-Chul ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 78~87
This article suggests the radionuclides which should be considered more important to the offsite consequence assesment during a nuclear power plant accident. For this purpose, the relative importance to the early health effects of released radionuclides on the major organs during the accident is estimated under the assumption of the same release fraction. The inventories of the 25 elements, 54 nuclides selected in the Reactor Safety Study are calculated by ORIGEN 2 code. The organs of interest in the estimation are G. I. track, bone marrow, thyroid and lung. The result shows the relative potential importance of radionuclides as follows: For G.I. track, Np, Ce, Ru, Y, and Zr are of importance in sequence, Np, I, La, Sr, Ba for bone marrow, I and Te for thyroid, Cm, Ce, Ru, Pu, Zr for lung. In addition to iodine and noble gases, therefore, the potential contribution of those nuclides listed above to the offsite consequences should not be overlooked for some accidents of particular sequence.
An Radiological Assessment Resulting from Accident during Transportation of Irradiated PWR Fuel
Yoon, Yeo-Chang ; Ha, Chung-Woo ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 88~94
The radiological impacts due to transportation of irradiated PWR fuel by truck were assessed for incident-free and accident conditions with. the computer code INTERTRAN. The resulting collective doses exposure to different subgroups of the public and of the workers were determined. Resulting collective doses for crewman and the public sharing the transport link and living in a corridor on either side of the route are small. All attempts to quantify the risk from the transport suffer from a lack of good input data. It is in these areas that the most important advances can be made.
ALARA for Nuclear Power Plant
Kang, Chang-Soon ;
Journal of Radiation Protection and Research, volume 13, issue 2, 1988, Pages 95~98