• Title/Summary/Keyword: Effective radiation area

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Quantitative Analysis of the Condensation Characteristics with Solar Radiations and Inner Temperature of the Tilted Box (일사량과 경사진 육면체 내부의 온도변화에 따른 응축특성에 관한 정량적 연구)

  • Lee, Cheun-Gi;Koh, Young-Ha;Kim, Byung-Chul
    • Journal of the Korean Solar Energy Society
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    • v.31 no.1
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    • pp.44-50
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    • 2011
  • The solar radiation, inner temperature of the tilted box and the amount of condensed water were measured to find the most effective purified water production system. The inner temperature of the tilted box was related with solar radiation that was affected by sunshine and cloud. With analyzing those relationships of the solar radiation, inner box temperature, the angle of tilted boxes and amounts of water condensation optimal collecting system area could be calculated.

Doses of Pediatric and X-ray Examination Assistants according to Changes in Pediatric X-ray Exposure Conditions (소아 X선 촬영조건 변화에 따른 소아 및 촬영보조자 선량)

  • Beom-Jin Jang;Ha-Yun Nam;Hye-Min Shin;Dong-Min Yun;Seung-Kook Lee;In-Hwa Jang;Sungchul Kim
    • Journal of radiological science and technology
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    • v.46 no.5
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    • pp.409-415
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    • 2023
  • Although pediatric X-ray examinations are continuously increasing, there are not many studies on the radiation exposure to children and X-ray examination assistants according to X-ray Exposure conditions. Accordingly, we measured the radiation exposure dose of pediatric and X-ray examination assistants according to the standard guidelines and clinical average X-ray Exposure conditions when X-ray examination 10-year-old children. The effective dose and organ dose to pediatric were measured using an Dose area production meter and Monte Carlo-based PCXMC program, and the exposure dose of X-ray examination assistants was measured using an ion-chamber. When performing abdominal supine AP projection, the effective dose to children was up to 2.38 times higher under clinical average X-ray Exposure conditions than the standard guidelines. In addition, during abdominal supine AP projection, the radiation exposure dose to the X-ray examination assistants was highest on the hands at 0.0148 ~ 0.0709 mSv, and exposure dose could be reduced by up to 35% when wearing protective gloves. In conclusion, because the X-ray Exposure conditions used in clinical are unnecessarily high, unnecessary medical radiation exposure could be reduced if appropriate X-ray Exposure conditions and the radiation field area were minimized and the assistant wore shielding gloves.

Natural radioactivity level in fly ash samples and radiological hazard at the landfill area of the coal-fired power plant complex, Vietnam

  • Loan, Truong Thi Hong;Ba, Vu Ngoc;Thien, Bui Ngoc
    • Nuclear Engineering and Technology
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    • v.54 no.4
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    • pp.1431-1438
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    • 2022
  • In this study, natural radioactivity concentrations and dosimetric values of fly ash samples were evaluated for the landfill area of the coal-fired power plant (CFPP) complex at Binh Thuan, Vietnam. The average activity concentrations of 238U, 226Ra, 232Th and 40K were 93, 77, 92 and 938 Bq kg-1, respectively. The average results for radon dose, indoor external, internal, and total effective dose equivalent (TEDE) were 5.27, 1.22, 0.16, and 6.65 mSv y-1, respectively. The average emanation fraction for fly ash were 0.028. The excess lifetime cancer risks (ELCR) were recorded as 20.30×10-3, 4.26×10-3, 0.62×10-3, and 25.61×10-3 for radon, indoor, outdoor exposures, and total ELCR, respectively. The results indicated that the cover of shielding materials above the landfill area significantly decreased the gamma radiation from the ash and slag in the ascending order: Zeolite < PVC < Soil < Concrete. Total dose of all radionuclides in the landfill site reached its peak at 19.8 years. The obtained data are useful for evaluation of radiation safety when fly ash is used for building material as well as the radiation risk and the overload of the landfill area from operation of these plants for population and workers.

The Evaluation of Patients' Radiation Dose During TACE of Interventional Radiology (TACE의 중재적 시술시 환자의 피폭선량 평가)

  • Lee, Seung-Youl;Lim, Hyun-Soo;Han, Man-Seok
    • Journal of radiological science and technology
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    • v.34 no.3
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    • pp.209-214
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    • 2011
  • Goal of this study was to measure effective radiation dose of highly exposed patients who were treated by TACE, interventional radiology from June to September 2010. The effective radiation dose was approximately measured by weighted DAP (dose area product) with the ionization chamber which is inserted in angiography equiment (Philips Allura Xper FD 20). Radiation dose was measured by TLD which was attached to patients' thyroid and genital gland. The average of ED (effective dose) was 18.43${\pm}$6.63 mSv per person and the average of radiation dose of thyroid and genital gland was 0.37 mSv, 0.77 mSv, respectively. The mean radiation dose of operators who wear the protector was 0.07 mSv for thyroid, and 0.01 mSv for genital gland, respectively. All staffs involved in TACE treatment, have to keep them aware and use the appropriate protectors to reduce the radiation dose of patient.

Analysis of Minimum Detectable Activity Concentration of Water Samples and Evaluation of Effective Dose (물 시료의 최소검출가능 농도 분석과 유효선량 평가)

  • Jang, Eun-sung;Kim, Yang-su;Lee, Sun-young;Kim, Jung-Soo
    • Journal of the Korean Society of Radiology
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    • v.14 no.7
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    • pp.857-862
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    • 2020
  • In March 2011, a tsunami off Japan caused radioactive material that had seeped into the sea from the Fukushima nuclear accident to flow to the Pacific Ocean, causing pollution to sea life. For a comparative evaluation with the area surrounding the site of a nuclear power plant by the release of radioactive materials, an area 20 to 30 km away from the emergency protection plan area was selected as a comparative point considering weather conditions, population distribution, etc. In addition, the government intends to analyze the minimum detection radiation received by residents around the nuclear power plant and evaluate the effective dose. Analysis of tritium radiation from water samples showed that most of the samples were not detected and that 0.0014 % to 0.777 % of the annual legal standard of 1 mSv for the general public had little effect on the human body. Therefore, the measurement and analysis of water samples around the nuclear power plant site is expected to help relieve anxiety, such as exposure to the general public and neighboring residents due to radiation release.

A Study on Structural Shielding Design of Afterloading Therapy Room (강내치료실 차폐에 대한 고찰)

  • Yun, Suk-Rok;Kim, Myung-Ho;Shin, Dong-Oh
    • The Journal of Korean Society for Radiation Therapy
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    • v.2 no.1
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    • pp.31-40
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    • 1987
  • In the case of designing a high dose rate remote controlled afterloading treatment room with existing hospital facilities. We must construct the effective protective barriers so as to reduce the primary and scattered radiation up to the maximum permissible dose level. It is difficult to reinforce the barrier thickness of the shielding requirements because of the limited space and the problem of the existing building structure at the surrounding area. Therefore we can reduce the intensity of primary radiation to the required degree at the location of interest with installing the appropriate I shaped Pb barriers between the radiation source and the shielding wall of the concrete. As a result, it was possible to reduce the intensity of the primary radiation below the M.P.D level by using additional Pb barriers instead of increasing thickness of concrete wall.

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Autonomous exploration for radioactive sources localization based on radiation field reconstruction

  • Xulin Hu;Junling Wang;Jianwen Huo;Ying Zhou;Yunlei Guo;Li Hu
    • Nuclear Engineering and Technology
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    • v.56 no.4
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    • pp.1153-1164
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    • 2024
  • In recent years, unmanned ground vehicles (UGVs) have been used to search for lost or stolen radioactive sources to avoid radiation exposure for operators. To achieve autonomous localization of radioactive sources, the UGVs must have the ability to automatically determine the next radiation measurement location instead of following a predefined path. Also, the radiation field of radioactive sources has to be reconstructed or inverted utilizing discrete measurements to obtain the radiation intensity distribution in the area of interest. In this study, we propose an effective source localization framework and method, in which UGVs are able to autonomously explore in the radiation area to determine the location of radioactive sources through an iterative process: path planning, radiation field reconstruction and estimation of source location. In the search process, the next radiation measurement point of the UGVs is fully predicted by the design path planning algorithm. After obtaining the measurement points and their radiation measurements, the radiation field of radioactive sources is reconstructed by the Gaussian process regression (GPR) model based on machine learning method. Based on the reconstructed radiation field, the locations of radioactive sources can be determined by the peak analysis method. The proposed method is verified through extensive simulation experiments, and the real source localization experiment on a Cs-137 point source shows that the proposed method can accurately locate the radioactive source with an error of approximately 0.30 m. The experimental results reveal the important practicality of our proposed method for source autonomous localization tasks.

Study on the Dosimetry and Assessment of Terrestrial Radiation Exposure (지각 방사선에 의한 피폭선량측정 및 해석)

  • Jun, Jae-Shik;Oh, Hi-Peel;Ha, Chung-Woo
    • Journal of Radiation Protection and Research
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    • v.15 no.2
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    • pp.87-100
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    • 1990
  • For the quantitative evaluation and assessment of radiation exposure from terrestrial component of natural environmental radiation, successive thermoluminescence dosimetry and periodical in-situ gamma ray spectrometry were carried out for a period of 24 months. LiF PTFE dise TLDs and $3&{\phi}{\times}3'$cylindrical NaI(Tl)scintill ation detector in association of portable multichannel analyzer (4096 ch) were used in this study. The doses measured were evaluated and assessed in terms of effective dose equivalent. As a concomitant output, the dose equivalent due to ionizing component of cosmic ray was able to be evaluated. According to the results obtained in terms of variance weighted mean, the annual effective dose equivalents of terrestrial gamma ray and cosmic ray ionizing component in Taejeon area came out to be $564{\pm}4\;{\mu}Sv(64.8{\pm}0.5nSv{\cdot}h^{-1}$ and $300{\pm}2\;{\mu}Sv(34.3{\pm}0.2nSv{\cdot}h^{-1}$, respectively, which are reasonable comparably with that appeared in UNSCEAR Report[28]as per caput annual effective dose equivalent in 'areas of normal background radiation'.

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Public Perception and Communication Patterns Pertaining to Nuclear Power in Korea: Focusing on the Transition Period from Pro-nuclear to De-nuclear Policy

  • Eunok Han;Yoonseok Choi
    • Journal of Radiation Protection and Research
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    • v.47 no.4
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    • pp.226-236
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    • 2022
  • Background: An effective communication strategy for reducing conflicts in South Korea has been designed through the analysis of public perception and communication variables on nuclear power under the conditions of rapidly changing nuclear power policies. Materials and Methods: This study conducted both qualitative research through group discussions based on social psychology and quantitative research through surveys. Results and Discussion: Nuclear power plant (NPP) area residents in favor of nuclear power indicated higher levels of communication, safety perception, and contribution than those against it. NPP area residents trusted the civilian expert groups (18.3%) and local government (17.3%) the most, while metropolitan city residents trusted the Nuclear Safety and Security Commission and the Korea Institute of Nuclear Safety (20.7%) the most. In determining nuclear power policy, both the NPP area residents (18.1%) and metropolitan city residents (17.1%) prioritized safety, health, and the environment. While metropolitan city residents thought that energy security and economic growth (16.4%) were important, NPP area residents thought the current issue of spent fuel rods (14.1%) to be important. Conclusion: It is necessary for the nuclear power industry to have and actively implement communication and conflict resolution strategies based on the patterns obtained in the study results.

A study on the elimination of static electricity by use of beta radiation source (Beta 방사선원을 이용한 정전기 제거법에 대한 고찰)

  • 임용규
    • 전기의세계
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    • v.14 no.3
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    • pp.28-33
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    • 1965
  • This experiment is based on "the feasible improvement studies for an eliminating device of the static electricity which applies the ionizing effect of beta radiation." In order to accomplish this object, the following problems were necessarily considered to investigate and to determine. The efficiency of the elimination of static electricity was determined by means of measuring the ion current between electrically charged plates with micro-ammeter. The effects of various factors, i.e., the distance between charged plate and radiation source, the activity of radiation source, the electric otential and the area of the charged plate, the shape of the source housing, the lining of backscattering material (Pb) on the source housing surface and blowing of ionized air, on the static electricity eliminating efficiency were studied. The beta radiation sources used in this experiment were S$^{35}$ and Sr$^{90}$ -Y$^{90}$ . It was revealed that ion current increased with source activity, the electric potential and area of the plates, the lead (Pb) lining on the surface of the source housing and the velocity of the ionized air blowing. As one could expect the S$^{35}$ was more effective to increase the ion current since it is known to be a higher specific ionization source than Sr$^{90}$ -Y$^{90}$ . The detailed result and performance of the eliminating device of the static electricity are described here.ibed here.

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