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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 34, Issue 4 - Dec 2009
Volume 34, Issue 3 - Sep 2009
Volume 34, Issue 2 - Jun 2009
Volume 34, Issue 1 - Mar 2009
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ANALYSIS OF THE LiF:Mg,Cu,Si TL AND THE LiF:Mg,Cu,P TL GLOW CURVES BY USING GENERAL APPROXIMATION PLUS MODEL
Chang, In-Su ; Lee, Jung-Il ; Kim, Jang-Lyul ; Oh, Mi-Ae ; Chung, Ki-Soo ;
Journal of Radiation Protection and Research, volume 34, issue 4, 2009, Pages 155~164
In this paper, we used computerized glow curve deconvolution (CGCD) software with several models for the simulation of a TL glow curve which was used for analysis. By using the general approximation plus model, parameters values of the glow curve were analyzed and compared with the other models parameters (general approximation, mixed order kinetics, general order kinetics). The LiF:Mg,Cu,Si and the LiF:Mg,Cu,P material were used for the glow curve analysis. And we based on figure of merits (FOM) which was the goodness of the fitting that was monitored through the value between analysis model and TLD materials. The ideal value of FOM is 0 which represents a perfect fit. The main glow peak makes the most effect of radiation dose assessment of TLD materials. The main peak of the LiF:Mg,Cu,Si materials has a intensity rate 80.76% of the whole TL glow intensity, and that of LiF:Mg,Cu,P materials has a intensity rate 68.07% of the whole TL glow intensity. The activation energy of LiF:Mg,Cu,Si was analyzed as 2.39 eV by result of the general approximation plus(GAP) model. In the case of mixed order kinetics (MOK), the activation energy was analyzed as 2.29 eV. The activation energy was analyzed as 2.38 eV by the general order kinetics (GOK) model. In the case of LiF:Mg,Cu,P TLD, the activation energy was analyzed as 2.39 eV by result of the GAP model. In the case of MOK, the activation energy was analyzed as 2.55 eV. The activation energy was analyzed as 2.51 eV by the GOK model. The R value means different ratio of retrapping-recombination. The R value of LiF:Mg,Cu,Si TLD main peak analyzed as
value analyzed as
. The R of LiF:Mg,Cu,P TLD analyzed as
value means different ratio of initial thermally trapped electron density-initial trapped electron density (include thermally disconnected trap electrons density). The
value was analyzed as
which was the difference from LiF:Mg,Cu,Si TLD. The deep trap electron density of LiF:Mg,Cu,Si was higher than the deep trap electron density of LiF:Mg,Cu,P.
OPERATIONAL EXPERIENCE OF A TWO-DOSIMETER ALGORITHM FOR BETTER ESTIMATION OF EFFECTIVE DOSE AT KOREAN NUCLEAR POWER PLANTS
Kim, Hee-Geun ; Kong, Tae-Young ;
Journal of Radiation Protection and Research, volume 34, issue 4, 2009, Pages 165~169
Two dosimeters are provided to radiation workers participating in tasks where high radiation exposure is expected during maintenance at nuclear power plants. At Korean nuclear power plants, two dosimeters are currently provided for tasks where exposure rates exceed 1 mSv/hr, the difference of equivalent dose to specific parts of the body is more than 30% and an exposure of more than 2 mSv is expected in a single task. These conditions for the provisioning of two dosimeters are based on previous field test results, and it is recommended that the dosimeters be worn on the chest and back. It was also found that the workers felt it was more convenient when they wore two dosimeters on chest and back rather than on chest and head. After the application of previous field test results to practice, it was found that the calculated effective dose for workers during radiation work was lower than the maximum dose of chest or back dosimeter by approximately 10%-30%. This performance is regarded not only to meet the international guideline but also to provide convenience for workers during radiation work.
Nuclide Identification of Gamma Ray Energy Peaks from an Air Sample for the Emergency Radiation Monitoring
Byun, Jong-In ; Yoon, Seok-Won ; Choi, Hee-Yeoul ; Yim, Seong-A ; Lee, Dong-Myung ; Yun, Ju-Yong ;
Journal of Radiation Protection and Research, volume 34, issue 4, 2009, Pages 170~175
For the emergency radiation monitoring using gamma spectrometry, we should sufficiently survey the background spectra as environmental samples with systematic nuclide identification method. In this study, we obtained the gamma ray energy spectrum using a HPGe gamma spectrometry system from an air sample. And we identified nuclide of the gamma ray energy peaks in the spectrum using two methods -1) Half life calculation and 2) survey for cascade coincidence summing peaks using nuclear data. As the results, we produced the nuclide identification results for the air sample.
An Analysis of Radiation Field Characteristics for Estimating the Extremity Dose in Nuclear Power Plants
Kim, Hee-Geun ; Kong, Tae-Young ;
Journal of Radiation Protection and Research, volume 34, issue 4, 2009, Pages 176~183
Maintenance on the water chamber of steam generator during outage in nuclear power plants (NPPs) has a likelihood of high radiation exposure to whole body of workers even short time period due to the high radiation exposure rates. In particular, it is expected that hands would receive the highest radiation exposure because of its contact with radiation materials. In this study, characteristic analysis of inhomogeneous radiation fields for contact operations was conducted using thermoluminescent dosimeter (TLD) readouts from the application tests of two-dosimeter algorithm to Korean NPPs in 2004. It is regarded that inhomogeneous radiation fields for contact operations in NPPs are dominated by high energy photons. In addition, field tests for workers who participated in maintenance on the steam generator during outage at Ulchin NPPs in 2009 and pressure tube replacement at Wolsong NPPs in 2009 were conducted to analyze radiation fields and to estimate the extremity dose. As a result, radiation fields were dominated by high energy photons.
An Internal Tritium Concentration Analysis in Urine Samples as a Function of Submission Time after Airborne Tritium Intake at Korean Pressurized Heavy Water Reactors
Kim, Hee-Geun ; Kong, Tae-Young ; Jeong, Woo-Tae ; Kim, Seok-Tae ;
Journal of Radiation Protection and Research, volume 34, issue 4, 2009, Pages 184~189
In pressurized heavy water reactors, workers who enter radiation controlled areas must submit their urine samples to health physicists after radiation work; these samples are then used to monitor internal radiation exposure from tritium intake. This procedure assumes that the samples submitted represent tritium concentration inside the body at equilibrium. According to both technical reports from the International Commission on Radiological Protection and experimental results from Canadian nuclear utilities, tritium inside the body generally reaches equilibrium concentration after approximately 2-3 hours of intake. In practice, urine samples can be submitted either before the 2 hours mark or after several hours of radiation work because of the numerous tasks that workers must perform and their frequent entries during nuclear power plant maintenance. In this paper, tritium concentration in workers' urine samples was measured as a function of time submitted after radiation work. Based on the measurement results, changes in the tritium concentration inside the body and its effect on internal dose assessment were then analyzed. As a result, it was found that tritium concentration reaches equilibrium concentration before the 2 hours mark for most workers' urine samples.
Analysis of 766 keV Gamma Peak from NPP Environmental Samples
Kim, Wan ; Lee, Hae-Young ; Yang, He-Sun ; Park, Hae-Soo ; Kim, Bong-Kuk ; Park, Hwan-Bae ; Kim, Hong-Joo ; Lee, Sang-Hoon ;
Journal of Radiation Protection and Research, volume 34, issue 4, 2009, Pages 190~194
Gamma spectral results for macroalgae samples taken from the environment of Ulchin nuclear power plants in Korea (east coast), showed 766 keV peaks, which were identified as
by several research institutes. After the enhancement of liquid radioactive waste disposal facility at Ulchin NPP site, the
amount in the liquid radioactive waste outflow has drastically reduced, but the expected reduction in
specific activity from environmental samples did not actually show up on gamma spectroscopy. Detailed re-investigation revealed that along with 766 keV peak, other peaks (63, 92 and 1001 keV) from
decay series were also detected on spectroscopy, and that the measured half lives of the four peaks were very close to known half life of
decay series, which is 24.1 day. The measured gamma yield ratios of 766 keV peak to 1001 peak were very close to known ratio 0.35 for
. It is concluded that 766 keV peaks on gamma spectroscopy of Ulchin NPP environmental samples were mainly from
, which is one of naturally occurring radionuclides.
An Investigation on the Technical Background for Carbon-14 Monitoring in Radioactive Effluents
Kim, Hee-Geun ; Kong, Tae-Young ; Jeong, Woo-Tae ; Kim, Seok-Tae ;
Journal of Radiation Protection and Research, volume 34, issue 4, 2009, Pages 195~200
effluents to the environment. The activity of carbon-14, one of the radioactive effluents, in the environment is already high level and its effect on radiation exposure to the public and the environment is insignificant; thus, NPPs did not perform the carbon-14 monitoring in effluents in the past. By the way, effluents of noble gas and particulate radioactive materials originated from nuclear fuels has been continuously reduced due to both the advancement of manufacturing and integrity technology for nuclear fuels and the improvement of operation methods of NPPs. Futhermore, the portion of dose assessment by tritium and carbon-14 to the public has been relatively increased because the lower limit of detection for low-energy beta sources, such as tritium and carbon-14, is low due to the advancement of radiation detection technology. In this paper, the technical background for carbon-14 monitoring in nuclear facilities was investigated using United States technical reports and papers. This paper also reviews whether carbon-14 monitoring is necessary or not based on the investigated documents.