• Title/Summary/Keyword: 누설선량

Search Result 54, Processing Time 0.032 seconds

Indicating the Problem of Shielding Design and the Way of Estimating Radiation Leakage for CT Rooms located through Survey of Radiation Leakage : in the case of Busan and Gyung-nam Area (방사선 누설선량 조사를 통한 방어시설과 누설선량 평가방법에 대한 문제점 연구 : 부산, 경남 지역 CT실을 중심으로)

  • Yang, Won Seok;Choi, Jun-Hyeok;Shin, Woon-Jae;Min, Byung-In
    • The Journal of the Korea Contents Association
    • /
    • v.13 no.11
    • /
    • pp.768-777
    • /
    • 2013
  • The purpose of this study is to minimize radiation exposure to the workers and public members during CT examination. The objects are seven of the CT rooms in university hospitals and four of the CT rooms in clinics located in Busan and Gyung-nam area. The places of measurement for radiation leakage are 1) 3 m above the ground of shielding wall in the control room 2) particular space in the control room 3) worker's gate in the control room 4) the patient gate. Its values were calculated maximum leakage radiation per week(MLRW). As a result, the worker's gate of M clinic displayed the highest dose. When it was calculated by MLRW in classic method, it showed 1) $5.97{\pm}0.23$, 2) $0.50{\pm}0.02$, 3) $10.00{\pm}0.11$, 4) $2.37{\pm}0.47$ mR/week. All of them did not exceed limit for maximum permissible dose per week(MPDW). However, When MLRW of M clinic was calculated by empirical method, its value displayed $118.31{\pm}17.72$ mR/week.(MPDW>100 mR/week). Radiation leakage influenced in the control room(p<0.05). Therefore, The way of calculating MLRW must be developed and shielding wall in control room is designed 3 m above the ground for reducing dangerous of leakage radiation.

Measurement from Moving Vehicle Health Screening Outside of The Leakage Dose (이동건강검진차량에서 외부의 누설선량 측정)

  • Han, Beom-Hee;Han, Sang-Hyun;Mo, Eun-Hee;Kim, Chong-Yeal
    • The Journal of the Korea Contents Association
    • /
    • v.15 no.3
    • /
    • pp.192-198
    • /
    • 2015
  • Checked out by the moving vehicle health checks for patients, practitioners, and the increase in radiation dose outside the vehicle, but an investigation into the leakage of radiation can still be negligible. In this study, through experimental results were as follows: Dose that occurs most often where the leak in the right door $1.14{\pm}1.75mR/h$, X-ray generator in terms of proximity to the top $0.65{\pm}1.25mR/h$, X-ray generator and away to the bottom in terms $0.91{\pm}1.25mR/h$, the adjacent rear detector in the upper part $96.98{\pm}158.88mR/h$ dose of the leak appeared in various locations. By measuring position from the rear of the adjacent detector $67.48{\pm}97.03mR/h$ dose had the highest leakage into. Generating device for diagnosis of radiation safety regulations regarding the maximum leakage dose per week, but all met back when it is displayed in the leakage dose Hourly rates do not ignore the leakage radiation dose were measured. Therefore, a mobile health screening in a vehicle outside of the leakage radiation dose to the liver and move on we are not interested twelve barrier leakage radiation dose of defense has a chance to re-evaluate the standards required, and move the vehicle health check using the X-ray increases as the dose per hour, depending on the criteria for choosing the appropriate measures that will require effort.

Health Screening Measures in a Car Outside of the Leakage Radiation Dose (건강검진차량에서 외부 누설방사선량 측정)

  • Han, Beom-Hee;Jung, Hong-Ryang
    • Proceedings of the Korea Contents Association Conference
    • /
    • 2011.05a
    • /
    • pp.191-192
    • /
    • 2011
  • X선 촬영을 통한 집단 건강검진은 경제성, 신속성, 대량처리 능력을 충족시키고 있으며 찾아가는 이동 의료서비스에서 중요한 부분을 차지하고 있다. 이와 함께 X선 촬영을 통한 집단 건강검진 시스템도 발전하여 간접촬영방식에서 Digital Radiography를 이용한 직접촬영방식으로 기술력이 향상되었고 이로써 검진차량에서 검진을 받는 환자나 종사자들에 대한 피폭선량의 증가하고 있으나 차량 외부의 누설방사선량에 대한 조사는 아직도 미미하다 할 수 있다[1]. 이에 본 연구에서 실험을 통한 결과는 다음과 같이 나타났다. 누설방사설량이 가장 많이 발생하는 곳은 출입문과 후면(검출기)에서는 우측, 양측면에서는 중앙이 가장 많은 누설방사선량이 나타났고, 측정위치별로는 검출기가 인접한 후면에서 누설방사선량이 가장 높았다. 기준치에 크게 벗어나지는 않았지만 누설방사선량은 다양하게 나타났다. 특히 후면에서의 누설방사선량은 기준치를 크게 웃돌아 방사선 차폐시설이 잘 갖추어지지 않은 것을 알 수 있으며 향후 이동검진차량의 방사선 차폐시설을 갖추는데 있어 각별한 관심이 필요하리라 사료된다.

  • PDF

Safety Simulation of Therapeutic I-131 Capsule Using GEANT4 (GEANT4를 이용한 치료용 I-131 캡슐의 안정성 시뮬레이션)

  • Jeong, Yeong-Hwan;Kim, Byung-Cheol;Sim, Cheol-Min;Seo, Han-Kyung;Gwon, Yong-Ju;Han, Dong-Hyun
    • The Korean Journal of Nuclear Medicine Technology
    • /
    • v.18 no.2
    • /
    • pp.57-61
    • /
    • 2014
  • Purpose Iodine (I-131) is one of the most widely used radioactive isotopes for therapeutic in the field of nuclear medicine. Therapeutic I-131 capsule is made out of lead to shield high energy radiation. Accurate dosimetry is necessarily required to perform safe and effective work for relative workers. The Monte Carlo method is known as a method to predict the absorbed dose distribution most accurately in radiation therapy and many researchers constantly attempt to apply this method to the dose calculation of radiotherapy recently. This paper aims to calculate distance dependent and activity dependent therapeutic I-131 capsule using GEANT4. Materials and Methods Therapeutic capsules was implemented on the basis of the design drawings. The simulated dose was determined by generating of gamma rays of energy to more than 364 keV. The simulated dose from the capsule at the distance of 10 cm and 100 cm was measured and calculated in the model of water phantom. The simulated dose were separately calculated for each position of each detector. Results According to the domestic regulation on radiation safety, the dose at 10 cm and 100 cm away from the surface of therapeutic I-131 capsule should not exceed 2.0 mSv/h and 0.02 mSv/h, respectively. The simulated doses turned out to be less than the limit, satisfying the domestic regulation. Conclusion These simulation results may serve as useful data in the prediction of hands dose absorbed by I-131 capsule handling. GEANT4 is considered that it will be effectively used in order to check the radiation dose.

  • PDF

Leakage and Scattered Radiation from X-ray Unit in Radiography (영상의학과 엑스선 발생장치의 누설 및 산란선량 측정)

  • Im, In-Chul;Lee, Jae-Seung;Kweon, Dae-Cheol
    • Journal of the Korean Society of Radiology
    • /
    • v.5 no.3
    • /
    • pp.155-159
    • /
    • 2011
  • The purposed of this study were measured the radiation exposure of patients and workers by generators, and the protection state for radiation facilities. The subject of the study by X-ray generators in university hospitals of capital area, we measured the maximum irradiation condition of 80 kVp, 200 mA, 0.1 second in the control entrance, control room window, entrance of radiography, adjacent site. The leakage dose per week was which the control entrance was 0.11 mR/week, control room window was 0.15 mR/week, entrance of radiography was 0.12 mR/week and adjacent site was 0.06 mR/week with X-ray unit the mean And the leakage mean dose was 0.11 mR/week. Diagnostic X-ray tubes must ensure that the leakage radiation in the maximum leakage dose in week emitted by the tube outside the useful beam does not exceed certain levels provided by standards.

Analysis of Dose Distribution of IORT Cone (IORT CONE의 선량분포에 관한 연구)

  • 김명세;김성규;신세원
    • Progress in Medical Physics
    • /
    • v.2 no.2
    • /
    • pp.141-148
    • /
    • 1991
  • A since authors started IORT for stomach cancer patient on 198, we developed various sized, shaped IORT cones for better clinical application and homogeneous surface and depth dose distribution. Authors concluded as following. 1. The shaping block should be fixed on the tray, not under the tray for homogeneous dose distribution. 2. The straight cone was showed better dose distribution than divergence cone. 3. The acryl cone was superior than the stainless-steel cone. 4. The acryl cover fixed on the end for IORT cone not only improvement of surface dose, but also homogenity of depth dose.

  • PDF

Analysis of Dose Distribution of Rectal IORT Cone (Rectal IORT cone의 선량분포에 관한 연구)

  • 김성규;신세원;김명세
    • Progress in Medical Physics
    • /
    • v.3 no.1
    • /
    • pp.45-52
    • /
    • 1992
  • Authors started IORT for stomach cancer patient on 1988 and rectal cancer on 1991. We devloped various sized. shaped IORT cones for better clinical application and homogeneous surface and depth dose distribution. Authors obtained results as following. 1. The acryl cover fixed on the end for rectal IORT cone not only improvement of surface dose but also flattness of dose distribution. 2. Dose distribution of elliptical cone were shown almost 100% at inner field. 3. The output with acryl cone size were similar output of made electron cone.

  • PDF

Verification of Clinical Usefulness of Jaw Tracking in IMRT (IMRT에 있어 Jaw Tracking 의 임상적 유용성 검증)

  • Kim, Jin-young;Kim, Ki-Hwan
    • Journal of the Korean Society of Radiology
    • /
    • v.14 no.2
    • /
    • pp.105-109
    • /
    • 2020
  • Intensity-modulated radiotherapy(IMRT) has disadvantages such as increasing the low doses of irradiation to normal tissues and accumulated dose for the whole volume by leakage and transmission of the Multi Leaf Collimator (MLC). The accumulated dose and low dose may increase the occurrence of secondary malignant neoplasms. For this reasons, the jaw tracking function of the TrueBeam (Varian Medical Systems, Palo Alto, CA) was developed to reduce the leakage and transmission dose of the MLC with existing linear accelerators. But quantitative analysis of the dose reduction has not been verified. Therefore, in the present study, we intended to verify the clinical possibility of utilizing the jaw tracking function in brain tumor with comparison of treatment plans. To accomplish this, 3 types of original treatment plans were made using Eclipse11 (Varian Medical Systems, Palo Alto, CA): 1) beyond 2 cm distance from the Organs At Risk (OARs); 2) within 2 cm distance from the OARs; and 3) intersecting with the OARs. Jaw tracking treatment plans were also made with copies of the original treatment planning using Smart LMC Version 11.0.31 (Varian Medical Systems, Palo Alto, CA). A comparison between the 2 types of treatment planning methods was performed using the difference of the mean dose and maximum dose to the OARs in cumulative Dose Volume Histogram (DVH). In the DVH comparison, the maximum difference of 0.5 % was observed between the planning methods in the case of over 2 cm distance, and the maximum of 0.6 % was obtained for within the 2 cm distance. For the case intersecting with the OAR, the maximum difference of 2 % was achieved. According to these results, it could be realized that the differences of mean dose and maximum dose to the OARs was larger when the OARs and PTV were closer. Therefore, treatment plans with the jaw tracking function consistently affected the dose reduction and the clinical possibility could be verified.

Measurement of the Spatial Scattering Dose by Opening, Closing Door and Installing Shielding : A Study on the Reduction of Exposure Dose in Radiography (문 개폐 여부와 차폐체 설치 유무에 따른 공간산란선량 측정 : X선 촬영 시 피폭선량 감소방안에 대한 연구)

  • Yoon, Hong-Joo;Lee, Yong-Ki;Lee, In-Ja
    • Journal of radiological science and technology
    • /
    • v.42 no.6
    • /
    • pp.477-482
    • /
    • 2019
  • Recently, due to the increased use of medical radiation, the radiation exposure of radiation workers should be considered as well as medical exposure of patients. And it is recommended to close the door during radiography. however, In this study, when the door was inevitably opened for radiography, the proposed method was to install the shield as a method of reducing the exposure dose. And its efficiency was analyzed. In simple chest radiography, the measurement point was changed according to the measurement location. Dose rate were measured 10 times for each condition using a dosimeter. And the average value was derived. Using this, the change of dose according to the opening and closing of the door and the installation of the shield was analyzed. Using this, we compared and analyzed the dose change according to the door opening and closing and the installation of the shield, and significance was verified through the SPSS ver. 24. Depending on whether the door was opened or closed, 11,215.35%, 159.0%, 101.9% increased in front of the door in the consol room, behind the wall and behind the lead glass. Depending on the installing of the shield, the 49.2%, 29.6%, 19.9%, 30.6% decrease in front of the door in the examination and consol room, behind the wall and lead glass. In addition, statistical analysis was showed that there were significant differences in both the results according to whether the door was opened or closed and shielding(p<.05). Close the door during radiography. However, when the door should be opened, it was confirmed that the dose rate were reduced by installing the shield. Therefore, to optimize radiation protection, it is recommended to install shields when opening the door.

Development of the Pushing Type Cutting Device to Dismantle Concrete Structure for Decommissioning of Nuclear Power Plant (원전해체 시 콘크리트 구조물 절단을 위한 밀기형 절단장치 개발)

  • Lee, Bong-Jae;Kwon, Yong-Kyu;Hong, Chang-Dong;Lee, Dong-Won;Min, Kyong-Nam
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.18 no.1
    • /
    • pp.103-111
    • /
    • 2020
  • Pulling-type cutting devices, which use a diamond wire saw, have been used generally for cutting concrete structures. In this study, a pushing-type cutting device with a collection cover was developed by overcoming the disadvantages of pulling-type devices. In this device, dry or liquid methods can be selected to cool frictional heat. Operation and leakage tests of the dust generated during the dismantling of a concrete structure were carried out, confirming the suitable operation of the fabricated cutting device; the leakage rate was approximately 1.7%. For a conservative evaluation, the internal dose of workers was estimated in dismantling the core center part of biological shield concrete with a specific activity of 99.5 Bq·g-1. The committed effective dose per worker was 0.25 mSv. The developed cutting device contributed to reducing radioactive concrete waste and minimizing worker exposure due to its easy installation. Therefore, it can be utilized as a cutting apparatus for dismantling not only reinforced concrete structures but also radioactive biological shield concrete in nuclear power plant decommissioning efforts.