• Title, Summary, Keyword: 개인선량계

Search Result 83, Processing Time 0.041 seconds

Development of Personal Dosimeter (개인 피폭선량 측정 시스템 개발)

  • Kwon, S.G.;Yi, U.K.;Lim, Hun;Sohn, C.H.;Kim, J.S.;Lee, C.J.
    • Proceedings of the KIEE Conference
    • /
    • /
    • pp.724-726
    • /
    • 2000
  • 일반적으로 개인방사선감시에 열형광선량계와 필름배지가 공식 개인선량계로 이용되어 왔고 현재까지도 가장 보편적으로 사용되고 있다. 하지만 최근에는 Si 다이오드와 G-M관을 이용한 능동형 개인피폭선량계가 개발 보급되고 있다. 개인피폭선량계는 누적선량을 실시간으로 알 수 있다는 장점을 가지고 있을 뿐만 아니라 선량률에 관한 정보도 제공하므로 높은 비용부담에도 불구하고 피폭관리의 용이함으로 인해 주목을 받고 있다. 따라서 본 연구는 수입에 의존해 온 개인피폭선량계를 대체하기 위해 반도체형 방사선 검출기를 설계하여 다양한 서비스를 부가할 수 있는 개인피폭선량계를 자체개발고, 선량계의 운영 및 판독을 위한 장치를 개발하였다.

  • PDF

A Study of Performance Characteristics for Electronic Personal Dosimeters in Photon and Electron Radiation Field (광자 및 베타 방사선에 대한 전자개인선량계의 성능특성연구)

  • Kim, Hyun-Ki;Kim, Bong-Hwan;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
    • /
    • v.22 no.2
    • /
    • pp.85-95
    • /
    • 1997
  • TLD and film badges have been traditionally used as formal dosimeters in personal monitoring and are still most widely used. Recently, electronic personal dosimeters based upon Si diode or miniature G-M tube were developed and are getting attractions due to their merits of active nature ; indication of dose rates and the commutative dose, and facilitation of record keeping and radiological control. Response characteristics of the electronic dosimeters including reproducibility, accuracy, linearity, energy and angular dependencies, detection threshold, and response time were examined for three commercial types ; EPD2, STEPHEN6000, and PD-3i. The results were compared with the relevant requirements of IEC standards and Ontario Hydro standards to conclude that their general performances were good. Some specific deficiencies, e.g. incapability of shallow dose measurement of STEPHEN6000, and PD-3i, however, should be corrected to be used as a formal dosimeter.

  • PDF

Evaluation of Usability and Radiation Dose Measurement Using Personal Radiation Exposure Dosimeter (방사선 개인피폭선량계를 이용한 피폭선량 측정 및 유용성 평가)

  • Kang, In-Seog;Ahn, Sung-Min
    • The Journal of the Korea Contents Association
    • /
    • v.14 no.11
    • /
    • pp.864-870
    • /
    • 2014
  • To propose a basis for the selection of personal dosimeters to measure radiation dose administration of radiation workers as a way to evaluate the usefulness dosimeter. For the dosimetry of the radiation workers 2012, during 1 year, 30 were radiation workers to measure personal dose. By personal exposure is measured cumulative dose, is investigated the performance of the TLD, PLD, OSLD. And comparing the measured value of each dosimeter dose and analyzed. Medical institutions, inspection work and quarterly confirmed the cumulative exposure dose of radiation workers. Using DAP and Ion-Chamber, to measure to compare TLD, PLD, OSLD dosimeter performance. A comparison of the directly through the X-ray dosimeter and The absolute value of the Ion-Chamber, OSLD more similar than in the TLD and PLD showed the dose values so the excellent ability to measure the results. Also in radiation generating area dose of radiation workers is higher than that in OSLD. Consequently, in terms of the individual exposure management OSLD is appropriated and beneficial than others.

Intercomparison Study of the Neutron Personnel Dosemeters (중성자 개인선량계 상호비교)

  • Kim, Bong-Hwan;Kim, Jang-Lyul;Chang, Si-Young
    • Journal of Radiation Protection and Research
    • /
    • v.23 no.1
    • /
    • pp.49-57
    • /
    • 1998
  • Domestic intercomparison study of the neutron personnel dosemeters was performed for the first time in Korea. Thirteen types of neutron dosemeters from twelve institutions took part in this intercomparison study and the $D_2O$ moderated Cf-252 source of KAERI was used for irradiation. Eight of the fifteen dosemeters submitted by each participant were divided into two groups and each group was irradiated with different doses of the simulated mixed fields of neutron and gamma. The participants assessed their dosemeter reading in terms of the personal dose equivalent, Hp(10), for both neutron and gamma dose. The ratio of the reported dose equivalent to the delivered dose equivalent for comparison between participants ranged from 0.55 to 1.34 for neutron, from 0.54 to 1.32 for gamma and from 0.75 to 1.20 for total dose. This intercomparison results show that all dosemeter processors, especially for neutron category, are able to pass the personnel dosemeter performance test which shall be enforced according to the ordinance of the MOST, No. 96-6.

  • PDF

Design of a TL Personal Dosimeter Identifiable PA Exposure and Development of Its Dose Evaluation Algorithm (후방피폭선량계측이 가능한 TL 개인선량계의 설계 및 선량평가 알고리즘 개발)

  • Kwon, J.W.;Kim, H.K.;Yang, J.S.;Kim, J.L.;Lee, J.K.
    • Journal of Radiation Protection and Research
    • /
    • v.29 no.3
    • /
    • pp.179-186
    • /
    • 2004
  • A single-dosimeter worn on the anterior surface of body of a worker was found to provide significant underestimation of dose to the worker when radiation comes from behind of the human body. Recently, several researchers suggested that this kind of underestimation can be corrected to a certain extent by using an extra dosimeter on the back. But this multiple dosimetry also has the disadvantages like overestimation lowering work efficiency or cost burden. In this study, a single dosimeter introducing asymmetric filters enabled to identify PA exposure was designed by monte-carlo simulation and experiments and its dose evaluation algorithm for AP-PA mixed radiation field was established. This algorithm was applicable to penetrating radiation which had the effective energy more than 100 keV. Besides, the dosimeter and algorithm in this study were possible to be applied to near PA exposure.

Radiation Dose Measurement of D-Shuttle Dosimeter for Radiation Exposure Management System (방사선피폭관리시스템를 위한 D-Shuttle 선량계의 방사선 선량측정)

  • Kweon, Dae Cheol
    • Journal of the Korean Society of Radiology
    • /
    • v.11 no.5
    • /
    • pp.321-328
    • /
    • 2017
  • The purpose of the study is to provide basic data for the management of individual exposure and the monitoring of natural radiation dose using D-Shuttle dosimeter (Chiyoda Technol Corporation, Tokyo, Japan). The dose was calculated using D-Shuttle dosimeter. The dose was 1.346 mSv when exposed for 400 days, the annual dose per year was 1.228 mSv/year and the average dose per hour was $0.014{\mu}Sv/hr$. Domestic individual external dose (1.295 mSv/year = Korea average natural individual external dose) and domestic additional dose per year is -0.0663 mSv/year. D-Shuttle is a personal dosimeter for radiation monitoring. It can be used as a very useful dosimeter for ALARA because of its excellent detection capability of radiation, real-time radiation exposure management, alarm function of radiation work, and efficient and easy to use personal radiation dose management.. Radiation monitoring equipment for radiation workers and local residents can be used for radiation monitoring in hospitals, industry, medical sites, nuclear accident areas and hazardous areas in non-destructive areas.

개인선량계의 국제상호비교연구

  • 윤석철;김장열;하정우
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • /
    • pp.875-881
    • /
    • 1995
  • 원자력 연구소는 국제원자력기구(IAEA/RCA) 주관하에 1990년부터 1993년 사이 3차에 걸쳐 실시한 개인선량계에 대한 국제상호비교에 참여하였다. 국제 상호비교에 참여하여 사용된 개인선량계는 방사선작업종사자에 대한 외부방사선으로부터 피폭관리를 위하여 기 사용중인 Taedyne Isotope 사의 PB-3타입의 열형광선량계이며 선량계판독용으로 Tdedyne 9150자동판독기를 사용하였다. 본 논문에는 3차에 걸쳐 국제상호비교결과를 요약하였으며 저 에너지의 엑스선에 경우를 제외하고 모든 조사방사선에 대해 0.78에서 1.07사이에 상대비율로 결과를 나타내었다. 또한 미국기준 ANSI Nl 3.11에 의해 성능을 시험한 결과 모든 조사방사선장에 대해서 허용기준 0.5이하를 나타내었다.

  • PDF

Development of Algorithm for Evaluation of the Dose with Thermoluminescence Dosimeter (열형광선량계에 의한 선량평가 알고리즘 개발)

  • Song, Myung-Jae;Kim, Hee-Keun;Ha, Chung-Woo;Lee, Tae-Young;Yoon, Suk-Chul
    • Journal of Radiation Protection and Research
    • /
    • v.17 no.2
    • /
    • pp.1-13
    • /
    • 1992
  • The purpose of this study is to develop an algorithm of TLD dose evaluation to meet all requirements stated in ANSI N13. 11-1983. It made the PB-3 TLD of Teledyne Isotopes an object of the development. Personal dosimetry performance testings of the development algorithm have been performed twice through the Atlan-Tech, INC. in accordance with the criteria of testing described in ANSI N13. 11-1983. As ,a result, it is assured that the developed algorithm has complied with all requirements stated in ANSI N13. 11-1983.

  • PDF