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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 35, Issue 4 - Dec 2010
Volume 35, Issue 3 - Sep 2010
Volume 35, Issue 2 - Jun 2010
Volume 35, Issue 1 - Mar 2010
Selecting the target year
A STUDY ON THE EFFECTS OF SCATTERING DOSE ON EYES AND THYROID FOR PANORAMAGRAPHY (Focus on TLD and PLD)
Jung, Yeun ; Dong, Kyung-Rae ; Kweon, Dae-Cheol ; Dieter, Kevin ; Goo, Eun-Hoe ; Ahn, Se-Youn ; Chung, Jae-Eun ;
Journal of Radiation Protection and Research, volume 35, issue 1, 2010, Pages 1~5
This study concerning the surface dose of eye and thyroid from panoramagraphy used thermoluminescent dosimeter (TLD) and photoluminescent dosimeter (PLD) to take measurements at ten hospitals in the Gwangju metropolitan area. The recommendations from ICRP 60 and ICRP 73 on the allowance standard for eye are 15 mSv and for thyroid is 1 mSv. The left eye TLD and PLD values are 0.19 mSv and 0.24 mSv respectively. The right eye TLD and PLD values are 0.23 mSv and 0.25 mSv respectively. Thyroid TLD and PLD values are 0.08 mSv and 0.25 mSv respectively and did not exceed the allowance standards(p<0.001). Also comparisons are made between TLD and PLD for each organ and PLD has higher dose measurements than TLD. There are statistically significant differences in left eye measurements and thyroid measurements (p<0.01). There is no significant difference in measurements for the right eye (p>0.05). The TLD and PLD measured dose from panoramagraphy instruments on eyes and thyroid from each hospital did not exceed the recommended dose from ICRP 60 for surface dose measurements. However, due to the probability of influence, consideration should be made for all levels of dose.
AN INTEGRATED APPROACH TO RISK-BASED POST-CLOSURE SAFETY EVALUATION OF COMPLEX RADIATION EXPOSURE SITUATIONS IN RADIOACTIVE WASTE DISPOSAL
Seo, Eun-Jin ; Jeong, Chan-Woo ; Sato, Seichi ;
Journal of Radiation Protection and Research, volume 35, issue 1, 2010, Pages 6~11
Embodying the safety of radioactive waste disposal requires the relevant safety criteria and the corresponding stylized methods to demonstrate its compliance with the criteria. This paper proposes a conceptual model of risk-based safety evaluation for integrating complex potential radiation exposure situations in radioactive waste disposal. For demonstrating compliance with a risk constraint, the approach deals with important exposure scenarios from the viewpoint of the receptor to estimate the resulting risk. For respective exposure situations, it considers the occurrence probabilities of the relevant exposure scenarios as their probability of giving rise to doses to estimate the total risk to a representative person by aggregating the respective risks. In this model, an exposure scenario is simply constructed with three components:radionuclide release, radionuclide migration and environment contamination, and interaction between the contaminated media and the receptor. A set of exposure scenarios and the representative person are established from reasonable combinations of the components, based on a balance of their occurrence probabilities and the consequences. In addition, the probability of an exposure scenario is estimated on the assumption that the initiating external factors influence release mechanisms and transport pathways, and its effect on the interaction between the environment and the receptor may be covered in terms of the representative person. This integrated approach enables a systematic risk assessment for complex exposure situations of radioactive waste disposal and facilitates the evaluation of compliance with risk constraints.
An Effects of Radiation Dose Assessment for Radiation Workers and the Member of Public from Main Radionuclides at Nuclear Power Plants
Kim, Hee-Geun ; Kong, Tae-Young ; Jeong, Woo-Tae ; Kim, Seok-Tae ;
Journal of Radiation Protection and Research, volume 35, issue 1, 2010, Pages 12~20
In a primary system at nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water conditions. Particularly,
are important radionuclides in respect of dose assessment for radiation workers and management of radioactive effluents. In this paper, the dominant contributors of radiation exposure for radiation workers and the member of public adjacent to NPPs were reviewed and the process of dose assessment attributable to those contributors were introduced. Furthermore, the analysis for some examples of radiation exposure to radiation workers and the public during the NPP operation was carried out. This analysis included the notable precedents of internal radiation exposure and contamination of demineralized water occurred in Korean NPPs. Particularly, the potential issue about the dose assessment of tritium and carbon-14 was also reviewed in this paper.
Fabrication of Ionization Chamber to Measure the Burnup of Spent Fuel
Park, Se-Hwan ; Eom, Sung-Ho ; Shin, Hee-Sung ; Lim, Hye-In ; Ha, Jang-Ho ; Kim, Han-Soo ;
Journal of Radiation Protection and Research, volume 35, issue 1, 2010, Pages 21~25
Burnup of spent fuel should be determined accurately for the safety control of spent fuel. Especially, it is necessary to measure the burnup profile along the nuclear fuel axis. In the present work, an ionization chamber was designed and fabricated to measure the gamma ray profile inside the guide tube of spent fuel. The ionization chamber was composed of three parts; induction part, gas-inlet part, and sensor part. The sensor part had two electrodes; cathode and anode. A guide electrode was considered in the ionization chamber design to make the ionization chamber to be inserted easily into the guide tube. Pure gas (argon and xenon) was inserted into the ionization chamber, and the leakage current and saturation curve were measured to determine the operation characteristics of the ionization chamber. The gamma ray radiation was also measured in relatively high dose environment. The gamma ray profile of the spent fuel will be measured with the ionization chamber.
Comparison of Non-Destructive Testing Images using
with Computed Radiography System
Kang, Sang-Mook ; Chol, Chang-Il ; Lee, Seung-Kyu ; Park, Sang-Ki ; Kim, Yong-Kyun ;
Journal of Radiation Protection and Research, volume 35, issue 1, 2010, Pages 26~33
A computed Radiography (CR) system by use of reusable Image Plate (IP) offers a convenient and reliable way to replace a conventional film-screen system for NDT (non-destructive testing) field. The quality of a radiography to detect a defect of welded objects depends on the procedure embracing several factors such as measurement conditions, image plate type/class, radiation energy, radiation type, and source to image plate distance. Also, the ability of images to detect a flaw reduces with increasing object thickness. In the study, the properties of gamma ray source were summarized for NDT field and inspection images of CR image system manufactured by FUJI were acquired using
with welded objects. We analyzed the gray scale of hole defect image by using XCAP image processing program and calculated the image contrast and SNR in definition. Also the sesitivities of image quality indicator(IQI) were calculated for hot and cooling tube image of
Actual Condition of Quality Control of X-ray Imaging System in Primary Care Institution: focused on Gwangju Metropolitan City
Dong, Kyung-Rae ; Lee, Seun-Joo ; Kweon, Dae-Cheol ; Goo, Eun-Hoe ; Jung, Jae-Eun ; Lee, Kyu-Su ;
Journal of Radiation Protection and Research, volume 35, issue 1, 2010, Pages 34~42
With the expanded use of radiation in modern medical practices, the most important issue in regards to efforts to reduce individual exposure dose is quality assurance. Therefore in order to study the present condition of quality assurance, the Gwangju Metropolitan City area was divided into five districts each containing ten hospitals. Four experiments were conducted: a reproducibility experiment for kVp, mA, and examination time (sec) intensity of illumination; half-value layer (HVL) measurement; and beam perpendicularity test matching experiment. The tube voltage reproducibility experiment for all fifty hospitals resulted in a 95.33% passing rate and mA and examination time both resulted in a 77.0% passing rate. The passing rate for intensity of illumination was 86.0% and 52.0% for HVL, which was the lowest passing rate of all four factors. For the beam perpendicularity test matching experiment, generally the central flux is matched to within
. Of all fifty hospitals 30.0% were beyond
. The results of the survey showed that 58% responded that they knew about quality assurance cycle. All fifty respondents stated that they have not received any training in regards to quality assurance at their current place of employment. Although quality assurance is making relative progress, the most urgent issue is awareness of the importance of quality assurance. Therefore, the implementation of professional training focusing on safety management and accurate quality assurance of radiation will reduce the exposure to radiation for radiologists and patients and higher quality imaging using less dosage will also be possible.
A Study on the Detection Ability of Minute Lesions in X-ray Using the Molybdenum Target
Yang, Da-Rae ; Dong, Kyung-Rae ; Park, Yong-Soon ; Ji, Youn-Sang ; Kim, Young-Keun ; Kim, Chang-Bok ;
Journal of Radiation Protection and Research, volume 35, issue 1, 2010, Pages 43~48
Beam quality is determined according to Xray tube's target material. In a range of between 22 kVp and 28 kVp, molybdenum target generates the characteristics energy between the average 17.9 kVp and 19.5 kVp, which produces the high contrast image of the breast. In this study, we used the Mo/Mo combination breast device and ALVIM TRM phantom and measured the detection ability of the minute lesion in the breast imaging throughout analyzing ROC curves. Assuming that an average subject thickness of the breast is 40 mm, the detection ability was not dependent on the kVp changes in a while dependent on both the mAs and thickness change. We can assure that it is not needed to increase the kVp for the imaging of breast which thickness is within the mean range of 40 mm.