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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 30, Issue 4 - Dec 2005
Volume 30, Issue 3 - Sep 2005
Volume 30, Issue 2 - Jun 2005
Volume 30, Issue 1 - Mar 2005
Selecting the target year
Carbon Fiber as Material for Radiation Fixation on Device : A comparative study with acrylic
Chie, Eui-Kyu ; Park, Jang-Pil ; Huh, Soon-Nyung ; Hong, Se-Mie ; Park, Suk-Won ; Kim, In-Ah ; Wu, Hong-Gyun ; Kim, Jae-Sung ; Kang, Wee-Saing ; Kim, Il-Han ; Ha, Sung-Whan ; Park, Charn-Il ;
Journal of Radiation Protection and Research, volume 30, issue 1, 2005, Pages 1~7
Radiation absorption parameters of carbon fiber panel were measured in comparison to acrylic panel.
sized 2mm thick carbon fiber panel and identical sized 6mm thick acrylic panel were placed in tray holder position and 0cm, 5cm, 10cm from surface of phantom. Radiation field size was
. 50MU of 4MV photon was irradiated to the phantom with dose rate of 300MU/min. Source-to-phantom distance was 120cm. Radiation dose was measured with 0.6cc Farmer-type ionization chamber with 1cm build-up. Measurement was repeated thrice and normalization was done to the dose of the open field. Radiation transmission rate of carbon fiber panel is approximately 1% lower than acrylic panel of equivalent thickness. However, considering the strength of the material, transmission rate is higher for carbon fiber panel. Although carbon fiber panel increases the radiation dose when attached to the surface for about 2%, it normalizes the radiation dose to 97-99% of irradiated dose which could have been lowered to as much as 5-7.5% with acrylic panel. As carbon fiber panel is stronger than acrylic panel, radiation fixation device could be made thinner and thus lighter and furthermore, with increased radiation transmission. This in turn makes carbon fiber more ideal material for radiation fixation device over conventionally used acrylic.
A study on the utilization of CT equipments
Cho, Pyong-Kon ; Oh, Yu-Whan ; Kim, Sung-Soo ; Choi, Jong-Hak ; Kim, You-Hyun ;
Journal of Radiation Protection and Research, volume 30, issue 1, 2005, Pages 9~15
This study was conducted to investigate the patient exposure dose during a CT examination and the present position in utilization of the CT equipments. To this end Questionnaire were sent out to 278 medical facilities registered at Korea Hospital Association and replies of 161 medical facilities were analyzed. The results were as follows ; 1) The distribution of CT examination was. Brain 40.7%, Abdomen 27.8%, Chest 15.7%, Spine 4.8%, Pelvis 4.1%, PNS 3.2%, Facial bone 2.5% and Extremity 1.1% respectively. 2) The statistics for dose index according to each part of examination were Brain 38.0mGy, Abdomen 12.0mGy for adults : Brain 13.6mGy, Abdomen 6.2mGy for infant. Our surveyed dose index appeared lower than the IAEA recommends. 3) Most medical facilities have selected the parameters for radiographic exposure in the range of
Planning of Optimal Work Path for Minimizing Exposure Dose During Radiation Work in Radwaste Storage
Park, Won-Man ; Kim, Kyung-Soo ; Whang, Joo-Ho ;
Journal of Radiation Protection and Research, volume 30, issue 1, 2005, Pages 17~25
Since the safety of nuclear power plant has been becoming a big social issue the exposure dose of radiation for workers has been one of the important factors concerning the safety problem. The existing calculation methods of radiation dose used in the planning of radiation work assume that dose rate does not depend on the location within a work space thus the variation of exposure dose by different work path is not considered. In this study, a modified numerical method was presented to estimate the exposure dose during radiation work in radwaste storage considering the effects of the distance between a worker and sources. And a new numerical algorithm was suggested to search the optimal work path minimizing the exposure dose in pre-defined work space with given radiation sources. Finally, a virtual work simulation program was developed to visualize the exposure dose of radiation doting radiation works in radwaste storage and provide the capability of simulation for work planning. As a numerical example, a test radiation work was simulated under given space and two radiation sources, and the suggested optimal work path was compared with three predefined work paths. The optimal work path obtained in the study could reduce the exposure dose for the given test work. Based on the results, tile developed numerical method and simulation program could be useful tools in the planning of radiation work.
Cholesteric Liquid Crystals as Multi-Purpose Sensor Materials
Lisetski, L.N. ;
Journal of Radiation Protection and Research, volume 30, issue 1, 2005, Pages 27~30
New possibilities are discussed for cholesteric liquid crystals (CLC) as sensor materials for detection of ionizing radiation, biologically active UV radiation, and the presence of hazardous vapors in atmosphere. A distinguishing property of CLC-based detectors is their 'bioequivalence', i.e., mechanisms of their response to external factors essentially imitate the corresponding mechanisms of biological tissues. Such detectors can ensure sufficiently high sensitivity to make feasible their use as alarm indicators or in biophysical studies. Specific examples ate given of sensor compositions and their response characteristics.
Bicyclic Derivatives of Aziridine - Materials for New Indicators of Radiation
Chebanov, V.A. ; Zbruyev, A.I. ; Desenko, S.M. ; Doroshenko, A.O. ; Vaschenko, V.V. ;
Journal of Radiation Protection and Research, volume 30, issue 1, 2005, Pages 31~34
The article is devoted to the study of some hi-and tricyclic derivatives of aziridine as materials lot newindicators of ionizing radiation. To create high sensitive materials some aspects of photo induced ring opening processes in aziridine derivatives in ethanol solutions and in polymeric matrix were studied and two steps character of the processes investigated was established. Two types of radioindicators were suggested and preliminary tested. The new way of synthesis of radiochromic derivatives of aziridine was developed and series of target compounds synthesized.
Design of a High Efficiency Neutron Detector Using a GEM
Kim, Yong-Kyun ; Park, Se-Hwan ; Kang, Sang-Mook ; Chung, Chong-Eun ;
Journal of Radiation Protection and Research, volume 30, issue 1, 2005, Pages 35~37
The radiation detector research group at KAERI has developed a high efficiency neutron detector using a Gas Electron Multiplier (GEM). The double GEM was fabricated and operated in an Ar/Isobutane mixture. For an application to a high efficiency neutron detector,
neutron converters coated on each surface of the multi GEM foils were considered. The optimized thickness of the thin film for a neutron detection was calculated with the MCNP and SRIM. The neutron efficiency was calculated by changing the chemical components of the thin film, and the thickness of the thin film. The thermalized neutrons were measured by a GEM detector with a thin neutron converter on the drift plate.
Development of Shielding Analysis System for the Reactor Vessel by
Kim, Ha-Yong ; Koo, Bon-Seung ; Kim, Kyo-Youn ; Lee, Chung-Chan ; Zee, Sung-Quun ;
Journal of Radiation Protection and Research, volume 30, issue 1, 2005, Pages 39~44
A new developing reactor isn't fixed the structure and the materials of reactor components. To perform the shielding analysis for a reactor vessel by
geometry, it takes much effort and time to modeling of source term according to the change of reactor components every time. Therefore, we developed the shielding analysis system for the reactor vessel by
geometry, which wasn't affected by the reactor core geometry. By using the developed shielding analysis system, we performed the shielding analysis for the reactor vessel of an integral reactor which has the hexagonal geometry of nuclear fuel assemblies in reactor core. We compared the results obtained from the developed system with those obtained from MCNP analysis. Because the results of developed shielding analysis system were more conservative than those of MCNP calculation, it is useful for shielding analysis. As we had developed the new shielding analysis system for a reactor vessel by
geometry, we reduced error of model for reactor core which was formerly designed by hand and saved the time and the effort to design source term model of reactor core.
Model for assessing the contamination of agricultural plants by accidentally released tritium
Keum, Dong-Kwon ; Lee, Han-Soo ; Kang, Hee-Suk ; Choi, Young-Ho ; Lee, Chang-Woo ;
Journal of Radiation Protection and Research, volume 30, issue 1, 2005, Pages 45~54
A dynamic compartment model was developed to appraise the level of the contamination of agricultural plants by accidentally released tritium from nuclear facility. The model consists of a set of inter-connected compartments representing atmosphere, soil and plant. In the model three categories of plant are considered: leafy vegetables, grain plants and tuber plants, of which each is modeled separately to account for the different transport pathways of tritium. The predictive accuracy of the model was tested through the analysis of the tritium exposure experiments for rice-plants. The predicted TFWT(tissue free water tritium) concentration of the rice ear at harvest was greatly affected by the absolute humidity of air, the ratio of root uptake, and the rate of rainfall, while its OBT(organically bound tritium) concentration the stowing period of the ear, the absolute humidity of air and the content of hydrogen in the organic phase. There was a good agreement between the model prediction and the experimental results lot the OBT concentration of the ear.