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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 20, Issue 4 - Dec 1995
Volume 20, Issue 3 - Sep 1995
Volume 20, Issue 2 - Jun 1995
Volume 20, Issue 1 - Mar 1995
Selecting the target year
Separation of Radiostrontium from Environmental Sample Using Strontim Selective Chromatographic Resin
Hong, Kwang-Hee ; Lee, Chang-Woo ; Choi, Yong-Ho ; Lee, Myung-Ho ;
Journal of Radiation Protection and Research, volume 20, issue 1, 1995, Pages 1~7
Strontium selective chromatographic material
was investigated for separation of radiostrontium from environmental soil and water sample. This chromatographic material has great capacity of binding of strontium ion in nitric acid media, and has selectivity to permit the separation of stontium from bulk amount of calcium. But the extraction of strontium was reduced by the other interfering ions such as K and Ba. So, in order to apply this material to the soil sample, prior removal treatment of K and Ba was needed. But the Sr-Spec material could provides simple and effective methods for the separation and removal of radiostrontium from liquid sample.
An Improvement on the Analysis Techniques of Environmental Radioactivity Around Nuclear Power Plants
Kim, Soong-Pyung ; Chae, Gyung-Sun ; Chung, Woon-Kwan ;
Journal of Radiation Protection and Research, volume 20, issue 1, 1995, Pages 8~15
An estimate of a change in radioactivity's circumstances around the nuclear power plant is validated with the results of the radioactivity measurements are compared. In this study, to further enhance the reliability of the results obtained from the environmental radioactivity measurements and analysis around the nuclear power plants that have been carried out up to the present. In the korea standard, there is the technical analysis guide for general stable chemical element's, but there is not the technical analysis guide for the radionuclei. therefore the environmental sample collection, the pretreatment of the sample and radionuclide analysis in the sample, the result's of the environmental radioactivity measurements by each organization, etc. are different. It is not sufficient for the database to forecasting a change in radioactivity's circumstances. A comparative study of collection and pretreatment techniques for the soil sample, the results by comparison, the method of minimizing the relative error are proposed. At one side of sample collection, there are going to considered that the surroundings of sample collection like the lay of the land, the provision of the selection standard for the area and pathway of radionuclide adhesion, the coherence of sample collection, etc.. at another side of pretreatment of the sample and measurement in the case of soil sample, how to do homogeneously the soil particle size and the standard tools, i.e. kinds of meshes, must to be selected.
Study on the Assessment of Dose Equivalent due to the Inhalation of
and Its Daughters in Indoor Air
Jun, Jae-Shik ; Chai, Ha-Seok ; Yi, Chul-Young ; Cho, Hyuck ; Ha, Chung-Woo ;
Journal of Radiation Protection and Research, volume 20, issue 1, 1995, Pages 16~24
Assesment of dose equivalent given by inhaled
and its progeny has been carried out based on the concentrations of
and its daughters in indoor air, and equilibrium factor between them measured by charcoal canister method and alpha spectrometry. Assuming the occupancy factor to be 0.8, and breathing rate to be
for public and
for occupational exposure, respectively, the regional lung dose 대valent and the resulting annual effective dose equivalent due to the inhalation of
and its daughters in indoor air were evaluated by use of three different lung models, namely, Jacobi-Eisfeld, James-Birchall and ICRP model.
Development of 3-D Stereotactic Localization System and Radiation Measurement for Stereotactic Radiosurgery
Suh, Tae-Suk ; Suh, Doug-Young ; Park, Sung-Hun ; Jang, Hong-Seok ; Choe, Bo-Young ; Yoon, Sei-Chul ; Shinn, Kyung-Sub ; Bahk, Yong-Whee ; Kim, Il-Hwan ; Kang, Wee-Sang ; Ha, Sung-Whan ; Park, Charn-Il ;
Journal of Radiation Protection and Research, volume 20, issue 1, 1995, Pages 25~36
The purpose of this research is to develop stereotactic localization and radiation measurement system for the efficient and precise radiosurgery. The algorithm to obtain a 3-D stereotactic coordinates of the target has been developed using a Fisher CT or angio localization. The procedure of stereotactic localization was programmed with PC computer, and consists of three steps: (1) transferring patient images into PC; (2) marking the position of target and reference points of the localizer from the patient image; (3) computing the stereotactic 3-D coordinates of target associated with position information of localizer. Coordinate transformation was quickly done on a real time base. The difference of coordinates computed from between Angio and CT localization method was within 2 mm, which could be generally accepted for the reliability of the localization system developed. We measured dose distribution in small fields of NEC 6 MVX linear accelerator using various detector; ion chamber, film, diode. Specific quantities measured include output factor, percent depth dose (PDD), tissue maximum ratio (TMR), off-axis ratio (OAR). There was small variation of measured data according to the different kinds of detectors used. The overall trends of measured beam data were similar enough to rely on our measurement. The measurement was performed with the use of hand-made spherical water phantom and film for standard arc set-up. We obtained the dose distribution as we expected. In conclusion, PC-based 3-D stereotactic localization system was developed to determine the stereotactic coordinate of the target. A convenient technique for the small field measurement was demonstrated. Those methods will be much helpful for the stereotactic radiosurgery.
Development of Dose Evaluation Algorithm for Film Badge Using ISO Reference Radiations
Kim, Jang-Lyul ; Chang, Si-Young ; Lee, Jai-Ki ;
Journal of Radiation Protection and Research, volume 20, issue 1, 1995, Pages 37~44
Since provisions on the technical criteria for personnel dosimetry was amended three years ago, several improvements in the technique of monitoring personnel doses by TLD have taken place, but for the photograpfic film as a personnel monitor, additional investigations should be carried out for its accuracy of dose estimates because of its wide use in the radiation involved industries. So, this paper describes the methods to develope dose evaluation algorithm for photographic film using ISO reference radiations by i) empirical formula, ii) degree-of-fit method, and iii) matrix approximation. These methods show a good agreement between irradiated and calculated dose within tolerance level represented in ANSI N13. 11, and can be used for the dose evaluation of X,
and/or radiation fields.
Measurement of Radiation Using Tissue Equivalent Phantom in ICR Treatment
Jang, Hong-Seok ; Suh, Tae-Suk ; Yoon, Sei-Chul ; Ryu, Mi-Ryeong ; Bahk, Yong-Whee ; Shinn, Kyung-Sub ;
Journal of Radiation Protection and Research, volume 20, issue 1, 1995, Pages 45~52
This study is to compare A point doses in human pelvic phantom by film dosimetry, computer planning and manual calculation by using of along-away table. We developed tissue equivalent human pelvic phantom composed of four pieces of cylindrical acryl tubes with water, to simulate intracavitary radiation (ICR) in patients with cervix cancer. When the phantom assembled from 4 pieces, it has a small space for inserting Fletcher-Suit-Delclos applicator like a human vagina. Fletcher-Suit-Delclos applicator inserted into the space was packed tightly with furacin gauzes, and three
sources with radioactivity of
were inserted into the tandem. For the film dosimetry, two pieces of X-OMAT V film (Kodak Co.) of which planes include point A, were arranged orthogonally in the slits between phantoms. A point dose and iso-dose curves were measured by means of optical densitometer. A point doses by film dosimetry, RTP system and manual calculation by using of along-away table were compared, and iso-dose curves by film dosimetry and computer planning were also compared. The dose of A point was 51.2cGy/hr by film dosimetry, 46.7cGy/hr by RTP system and 47.9 cGy/hr by along-away table. A point dose by computer planning was similar to the dose by calculation using of along-away table with acceptable accuracy
, however, the dose by film dosimetry was different from two others with about 10% error. Since most clinical beams contains a scatter component of low energy photons, the correlation between optical density and dose becomes tenuous. In addition, film suffers from several potential errors such as changes in processing conditions, interfilm emulsion differences, and artifacts caused by air pockets adjacent to the film. For these reasons, absolute dosimetry with film is impractical, however, it is very useful for checking qualitative patterns of a radiation distribution. In future, solid state dosimeter such as TLD must be used for the dosimetry of ionizing radiation. When considerable care is used, precision of approximately 3% may be obtained using TLD.
Assessment of Post-LOCA Radiation Fields in Service Building Areas for Wolsong 2, 3, and 4 Nuclear Power Plants
Jin, Yung-Kwon ; Kim, Yong-Il ;
Journal of Radiation Protection and Research, volume 20, issue 1, 1995, Pages 53~64
The radiation fields following the large loss of coolant accident (LOCA) have been assessed for the vital areas in the service building of Wolsong 2, 3, and 4 nuclear power plants. The ORIGEN2 code was used in calculating the fission product inventories in the fuel. The source terms were based upon the activity released following the dual failure accident scenario, i.e., a LOCA followed by impaired emergency core cooling (ECC). Configurations of the reactor building, the service building, and the ECC system were constructed for the QAD-CG calculations. The dose rates and the time-integrated doses were calculated for the time period of upto 90 days after the accident. The results showed that the radiation fields in the vital access areas were found to be sufficiently low. Some areas however showed relatively high radiation fields that may require limited access.