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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
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Journal of Radiation Protection and Research
Journal Basic Information
Journal DOI :
Korean Association for Radiation Protection
Editor in Chief :
Volume & Issues
Volume 38, Issue 4 - Dec 2013
Volume 38, Issue 3 - Sep 2013
Volume 38, Issue 2 - Jun 2013
Volume 38, Issue 1 - Mar 2013
Selecting the target year
Gross Beta Screening and Monitoring Procedure using Urine Bioassay for Radiation Workers of Radioisotope Production Facilities
Yoon, Seokwon ; Kim, Mee-Ryeong ; Park, Seyoung ; Pak, Min-Jeong ; Yoo, Jaeryong ; Jang, Han-Ki ; Ha, Wi-Ho ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 52~59
DOI : 10.14407/jrp.2013.38.2.052
The internal contamination screening method using gross beta measurement was performed for radioisotope workers. 24 h and spot urine samples from workers of medical isotope production facilities were collected and measured. Most of the results were similar with the background level of gross beta activity except for a specific worker. Gross beta activity was slightly increased in several hours after finishing work. And the environmental factor of production facilities causing internal contamination were estimated based on screening results. The additional detailed internal dose assessment must be followed after the screening for protection of workers. Moreover, a procedure was established to apply a simple internal contamination assessment for radiation workers.
Influence of Modelling Approaches of Diffusion Coefficients on Atmospheric Dispersion Factors
Hwang, Won Tae ; Kim, Eun Han ; Jeong, Hae Sun ; Jeong, Hyo Joon ; Han, Moon Hee ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 60~67
DOI : 10.14407/jrp.2013.38.2.060
A diffusion coefficient is an important parameter in the prediction of atmospheric dispersion using a Gaussian plume model, and its modelling approach varies. In this study, dispersion coefficients recommended by the U. S. Nuclear Regulatory Commission's (U. S. NRC's) regulatory guide and the Canadian Nuclear Safety Commission's (CNSC's) regulatory guide, and used in probabilistic accident consequence analysis codes MACCS and MACCS2 have been investigated. Based on the atmospheric dispersion model for a hypothetical accidental release recommended by the U. S. NRC, its influence to atmospheric dispersion factor was discussed. It was found that diffusion coefficients are basically predicted from a Pasquill- Gifford curve, but various curve fitting equations are recommended or used. A lateral dispersion coefficient is corrected with consideration for the additional spread due to plume meandering in all models, however its modelling approach showed a distinctive difference. Moreover, a vertical dispersion coefficient is corrected with consideration for the additional plume spread due to surface roughness in all models, except for the U. S. NRC's recommendation. For a specified surface roughness, the atmospheric dispersion factors showed differences up to approximately 4 times depending on the modelling approach of a dispersion coefficient. For the same model, the atmospheric dispersion factors showed differences by 2 to 3 times depending on surface roughness.
Calculation of Derived Investigation Levels for Uranium Intake
Lee, Na-Rae ; Han, Seung-Jae ; Cho, Kun-Woo ; Jeong, Kyu-Hwan ; Lee, Dong-Myung ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 68~77
DOI : 10.14407/jrp.2013.38.2.068
Derived Investigation levels(DILs) were calculated to protect the workers from the effects of both radiological hazard and chemical toxicity by uranium intake. Investigation Levels(ILs) of committed effective dose of 2 mSv
and uranium concentration of 0.3
in kidney, based on Korean Nuclaer Safety Act, Korean Occupational Safety and Health Act and current scientific studies of uranium intake were assumed. DILs of radiological hazard and chemical toxicity were then calculated based on the concentration of uranium in air of workplace, the lung monitoring and urine analysis, respectively. As a result, in case of the nuclear fuel fabrication plant where 3.5% enriched uranium is handled, derived investigation level(DIL) for the control of the concentration of uranium in the air of workplace assumed with 15-min acute inhalation was 0.6 mg
for all types of uranium. DILs for the control of the average concentration of uranium in air of workplace, assuming an 8-hour workday, were 15.21
of Type F uranium, 0.41-1.23 Bq
and 0.13-0.39 Bq
for Type M and Type S uranium, respectively. DILs for the lung monitoring assumed with a period of 6-month interval were 0.37-1.11 Bq and 0.39-1.17 Bq in acute and chronic inhalation for Type M, respectively and 0.30- 0.91 Bq and 0.19-0.57 Bq in acute and chronic inhalation for Type S, respectively. Since a detection limit of typical germanium detector for the measurement of 235U activity is 4 Bq, DILs calculated for the lung monitoring were not appropriate. DILs for urine analysis, for which an interval was assumed to be 1 month, were 14.57
based on chemical toxicity after acute inhalation. In addition, acute and chronic inhalation of Type M were calculated 2.85-8.58
based on the radiological hazard, respectively.
Change of Dose Exposure and Improvement of Image Quality by Additional Filtration in Mammography
Cho, Woo Il ; Kim, Young Kuen ; Lee, Gil Dong ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 78~90
DOI : 10.14407/jrp.2013.38.2.078
Recently, the interest on exposure to radiation is rising. The radiation exposure of mammography is higher in absorbed dose than of X-ray, therefore unnecessary exposure needs to be reduced, and higher image quality is needed. Generally, ray quality of the radiation imaging is an important factor that determines image quality and the amount of ray exposure, and they are affected by tube voltage and added filter. The X-ray energy that is exposed from mammography device is generally a continuous spectrum, which includes low energy that has minute influence on the image quality, and high energy that hinders contrast on image. Currently, molybdenum (Mo) and rhodium (Rh) are the most used added filters for mammography device, and they are used differently according to the energy region of X-ray. This study aims to find out the degree of reduction in exposure dose according to the thickness of aluminum (Al), and to study the changes in image quality and dose when the added filter plates that are made with niobium (Nb) or zirconium (Zr) are used, other than molybdenum (Mo) and rhodium (Rh), the two most used added filters that have similar atomic number and K-absorption regions as Nb and Zr. In this study, single-added filters of molybdenum (Mo), niobium (Nb), and zirconium (Zr) are used, and in some cases, Aluminum (Al) is combined with the single filters. In this case, image quality is considered to be improved depending on the type of added filters, and by using Aluminum (Al) filter together with the others, unnecessary X-ray of low energy would be absorbed, therefore the dose is expected to decrease without any influence when the concentration level becomes identical.
A Study on the Adoption of Cyclotron Decommissioning Plan Criteria by the Analysis of Domestic Relocation and Abroad Dismantling Practices
Woo, Rina ; Kim, Yongmin ; Song, Minchul ; Cho, Daehyung ; Lee, Jaesung ; Kim, Wantae ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 91~99
DOI : 10.14407/jrp.2013.38.2.091
There are many reasons for decommissioning of cyclotron such as not only age-related deficiency, any serious wear or damage but also relocation, upgrade and changing mission. Decommission of cyclotron in USA and EU give rise to a lot of low-level radioactive waste and costs. Various research on decommissioning of particle accelerator have been carried to reduce the cost of decommissioning in USA and EU. In USA, the NRC require DFP (Decommissioning Funding Plan) to authorized licenser by 10 CFR Part 30.35. To resolve radioactive waste problem and reduce the estimated cost of cyclotron decommissioning, we should consider technical aspects (decommissioning procedures, decontamination techniques, etc.) and safety aspects(residual radioactivity, the expected dose, etc) for decommissioning. In this study, we analyzed practical information on the decommissioning of cyclotron in ANL (Argonne National Laboratory) and Belgium (EU). And we investigated the experience on the cyclotron relocation from SNUH (Seoul National University Hospital) to SKKU (Sungkyunkwan University). From these results, we provide the basic data for establishing of relevant standards on domestic cyclotron decommissioning. It is necessary to adopt the DFP for safe and economic decommissioning and waste recycling. These result could be utilized for the establishment on the standards and useful requirements.
Development of a Needs Based Education Course on the Basics of Radiation
Nam, Jong Soo ; Won, Jong Yeoul ; Seo, Kyung Won ; Yoo, Hye Won ; Hwang, In Ah ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 100~105
DOI : 10.14407/jrp.2013.38.2.100
With the export of commercial nuclear power plants to UAE and that of a research reactor to Jordan, as well as the additional construction of domestic nuclear power plants, the demand of nuclear manpower is expected to increase sharply. Accordingly, nuclear manpower development is recently becoming an important issue. Major institutes involved in nuclear programs are well equipped with education and training procedures and resources. However, small and medium sized businesses have difficulties to educate their employees due to their limited resources and capacity for the education. Addressing the difficulties, this study is intended to develop and education course in accordance with the "Systematic Approach to Training (SAT)". For this, a survey is conducted on the need of education in small and medium sized businesses, based on which a pilot course on the basics of radiation is developed and operated. An assessment on the development and operation using a survey regarding participants response has shown high grades of performance, i.e. above 4.0 points (full mark: 5.0 points) on each level of expectancy, satisfaction and lecturers' capacity. The experience from this study will be used to develop other programs of nuclear power and ASME code, which are also identified from the need analysis.
Relation of Self-Efficacy and Cognition of Irradiated Food among High School Students
Han, Eun Ok ; Choi, Yoon Seok ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 106~118
DOI : 10.14407/jrp.2013.38.2.106
In this paper, we analyzed the Cognition of irradiated food and its relation with self-efficacy. The most important variables described behaviors based on health choices compared with the choice to choose irradiated food items. According to the survey, 33.1% of respondents said that the reason why irradiated food is considered to be a health risk is because "radiation is dangerous". 27.9% of respondents answered that "eating irradiated food is like eating a radioactive substance", 21.1% said radiated food is comparable to a "genetic variation in food" while 10.1% said "food goes bad during the irradiation process". On this basis, it is reasonable to conclude that respondents have a misunderstanding of irradiated food without reference to the general theory of irradiated knowledge. In this respect, it would be helpful to provide education showing that irradiated food is not related to eating harmful or genetically modified food to help high school students create informed opinions of irradiated food. In terms of relevance with health-specific self-efficacy, experience of acquiring information about irradiated food was marked at r=0.148 (p<0.01), experience of purchasing irradiated food was marked at r=0.077 (p<0.05), experience of eating irradiated food was marked at r=0.113 (p<0.01) while knowledge of irradiated food, attitude towards irradiated food and behavior was marked at r=0.103 (p<0.01), r=0.076 (p<0.05) and r=0.105 (p<0.01) respectively. This shows that self-efficacy is high when one has experience of acquiring information about irradiated food, purchasing or eating irradiated food resulting in a high level of knowledge, attitude and behavior. Education which serves to improve the level of self-efficacy needs to be provided along with an educational program which will increase the public's understanding of irradiated food. It is expected that if this education which increases the level of self-efficacy is provided together with correct information of irradiated food, behavior to choose and eat irradiated food will also improve.
Development of a simple laboratory-made radioactive source to check the integrity of a gamma spectrometry system with HPGe detector
Lee, Mo Sung ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 119~123
DOI : 10.14407/jrp.2013.38.2.119
A simple laboratory-made radioactive source to check the integrity of a gamma spectrometry system with HPGe detector was developed. The check source consists of radium-riched soil which was ground in size of less than 0.154mm and contained in air tight cylinderical vial, and provides photons with 12 distinct energies. The spectra of the check source were measured once a month during one year, analyzed the charactreictics of their peaks. When the gamma spectrometry system was in normal state, the areas and FWHMs of the gamma rays with more than 3% gamma emission rate in radium and its decay products was constant within standard deviation 2% and 3%, respectively, except 77 keV peak. And it was found that this check source can play a sufficient role to check the integrity of a gamma spectrometry system using 10 peaks in the range of 77 to 2202 keV.
Review of Contamination and Monitoring of On-site Groundwater at Foreign Nuclear Power Plants due to Unplanned Release
Sohn, Wook ; Lee, Gab-Bok ; Yang, Yang-Hee ;
Journal of Radiation Protection and Research, volume 38, issue 2, 2013, Pages 124~131
DOI : 10.14407/jrp.2013.38.2.124
Utilities have tried to ensure that radiological hazards to the environment and residents are kept as low as reasonably achievable by monitoring and controlling planned releases. However, since groundwater contamination was reported to occur due to unplanned releases mostly in the United States nuclear power plants, the interest of the stakeholders has increased to a point where it is now one of the most important issues in the United States nuclear power industry. This paper aims to help to implement an effective on-site groundwater monitoring program at domestic nuclear power plants by briefing the experiences of the United States nuclear power plants on groundwater contaminations and groundwater monitoring, and responses of the United States nuclear industry and regulator body for them.