• 제목/요약/키워드: effective dose equivalent

검색결과 100건 처리시간 0.029초

이동형 구내방사선촬영기와 벽걸이 구내방사선촬영기로 촬영한 치근단 방사선촬영에서 환자의 흡수선량과 유효선량 평가 (Absorbed and effective dose for periapical radiography using portable and wall type dental X-ray machines)

  • 한원정
    • 대한치과보철학회지
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    • 제50권3호
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    • pp.184-190
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    • 2012
  • 연구 목적: 이 연구는 상악 전치부와 하악 구치부 치근단 방사선촬영시 이동형 구내방사선촬영기와 벽걸이 구내방사선촬영기로 촬영한 경우에서 환자의 방사선량을 알아보고자 하였다. 연구 재료 및 방법: 방사선량 측정은 선량 측정용 두경부 마네킨의 23부위에 열형광선량계 소자를 위치시키고 해당 치근단 방사선촬영을 하였다. 열형광선량계 판독기로 흡수선량을 구하였고 방사선 조사된 조직의 비율을 곱하여 방사선 가중선량을 구하였다. 국제방사선방호위원회에서 2007년에 공지한 조직 가중계수를 이용하여 각 방사선촬영의 유효선량을 구하였다. 결과: 환자의 흡수선량은 이동형 구내방사선촬영기로 촬영한 상악 전치부와 이동형 및 벽걸이 구내방사선촬영기로 촬영한 하악 구치부 치근단방사선촬영의 경우 하악체에서 가장 높았다. 유효선량은 상악 전치부 치근단 방사선촬영에서는 이동형 촬영기로 촬영한 경우 $4{\mu}Sv$, 벽걸이 촬영기로 촬영한 경우 $2{\mu}Sv$였고 우측 하악 구치부 치근단 방사선촬영에서는 각각 $6{\mu}Sv$, $2{\mu}Sv$였다. 결론: 벽걸이 구내방사선촬영기보다 이동형 구내방사선촬영기로 촬영한 치근단 방사선촬영에서의 유효선량이 더 많기 때문에 술자는 구내방사선촬영기에 따른 방사선 노출 정도를 충분히 인지하고 이를 사용하여야 한다.

증기발생기 수실의 방사선장 특성 및 작업자 유효선량의 평가 (Characterization of Radiation Field in the Steam Generator Water Chambers and Effective Doses to the Workers)

  • 이춘식;이재기
    • Journal of Radiation Protection and Research
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    • 제24권4호
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    • pp.215-223
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    • 1999
  • PWR 원전 증기발생기 수실의 방사선장 특성과 그곳에서 작업하는 종사자의 유효선량을 몬테칼로 시뮬레이션으로 평가하였다. 선원항으로는 고리1호기 증기발생기 방사화물 분석결과가 사용되었으며 유효선량 평가에는 MCNP4A코드와 MIRD형 성별 수학적 인형 모의피폭체가 사용되었다. 수실 내부 방사선장은 U튜브 영역에서 내려오는 방사선이 지배적이었으며 극각에 대해 근사적으로 코사인 분포를 나타내었다 유효선량률은 표준성인과 체격이 작은 성인(이 목적으로 15세 모의피폭체가 사용되었다.)의 경우 각각 36.22$mSvh^{-1}$와 37.06$mSvh^{-1}$로서 체격의 영향은 경미했다. 한편, 모의피폭체의 머리, 가슴 및 하복부에 해당하는 위치에서 평가된 조사선량률과 에너지스펙트럼에 대해 ICRU47에서 주어진 주위선량당량 환산계수를 이용해 평가한 등가선량률은 각각 119, 71, 및 58 $mSvh^{-1}$로 나타났다. 따라서 개인선량계 판독에서 얻는 심부선량 또는 유효선량은 앞서 계산한 유효선량률의 2배 정도가 될 것으로 보인다. 이 사실은 일반적인 개인선량계의 경사입사 방사선에 대한 과대/과소 평가 특성과 함께 비정규, 고선량률 방사선장에 종사하는 작업자의 선량계측 계획 및 결과의 해석에 매우 신중해야 함을 알려준다.

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Prediction of radioactivity releases for a Long-Term Station Blackout event in the VVER-1200 nuclear reactor of Bangladesh

  • Shafiqul Islam Faisal ;Md Shafiqul Islam;Md Abdul Malek Soner
    • Nuclear Engineering and Technology
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    • 제55권2호
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    • pp.696-706
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    • 2023
  • Consequences of an anticipated Beyond Design Basis Accident (BDBA) Long-Term Station Blackout (LTSBO) event with complete loss of grid power in the VVER-1200 reactor of Rooppur Nuclear Power Plant (NPP) of Unit-1 are assessed using the RASCAL 4.3 code. This study estimated the released radionuclides, received public radiological dose, and ground surface concentration considering 3 accident scenarios of International Nuclear and Radiological Event Scale (INES) level 7 and two meteorological conditions. Atmospheric transport, dispersion, and deposition processes of released radionuclides are simulated using a straight-line trajectory Gaussian plume model for short distances and a Gaussian puff model for long distances. Total Effective Dose Equivalent (TEDE) to the public within 40 km and radionuclides contribution for three-dose pathways of inhalation, cloudshine, and groundshine owing to airborne releases are evaluated considering with and without passive safety Emergency Core Cooling System (ECCS) in dry (winter) and wet (monsoon) seasons. Source term and their release rates are varied with the functional duration of passive safety ECCS. In three accident scenarios, the TEDE of 10 mSv and above are confined to 8 km and 2 km for the wet and dry seasons, respectively in the downwind direction. The groundshine dose is the most dominating in the wet season while the inhalation dose is in the dry season. Total received doses and surface concentration in the wet season near the plant are higher than those in the dry season due to the deposition effect of rain on the radioactive substances.

Cancer Risk Assessment Due to Natural and Fallout Activity in Some Cities of Pakistan

  • Ahad A.;Matiullah Matiullah;Bhatti Ijaz A.;Orfi S.D.
    • Journal of Radiation Protection and Research
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    • 제31권1호
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    • pp.1-7
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    • 2006
  • The measured mean activities of $^{226}Ra,\;^{232}Th,\;^{40}K\;and\;^{137}Cs$ in the soil of Bahawalpur, Bahawalnagar and Rahimyar Khan Bistricts were 32.9, 53.6, 647.4 and 1.8 Bq $kg^{-1}$. The average absorbed dose rate calculated from these activities was 74.3 nGy $h^{-1}$ and the mean annual effective dose rate was found to be 0.46 mSv $y^{-1}$. Absorbed doses to different body organs were derived from annual effective doses using tissue weighting factors. Radiation induced fatal cancer risks were assessed by using ICRP 60 Model. Estimations incurred 184deaths per year due to cancer.

OPERATIONAL EXPERIENCE OF A TWO-DOSIMETER ALGORITHM FOR BETTER ESTIMATION OF EFFECTIVE DOSE AT KOREAN NUCLEAR POWER PLANTS

  • Kim, Hee-Geun;Kong, Tae-Young
    • Journal of Radiation Protection and Research
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    • 제34권4호
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    • pp.165-169
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    • 2009
  • Two dosimeters are provided to radiation workers participating in tasks where high radiation exposure is expected during maintenance at nuclear power plants. At Korean nuclear power plants, two dosimeters are currently provided for tasks where exposure rates exceed 1 mSv/hr, the difference of equivalent dose to specific parts of the body is more than 30% and an exposure of more than 2 mSv is expected in a single task. These conditions for the provisioning of two dosimeters are based on previous field test results, and it is recommended that the dosimeters be worn on the chest and back. It was also found that the workers felt it was more convenient when they wore two dosimeters on chest and back rather than on chest and head. After the application of previous field test results to practice, it was found that the calculated effective dose for workers during radiation work was lower than the maximum dose of chest or back dosimeter by approximately 10%-30%. This performance is regarded not only to meet the international guideline but also to provide convenience for workers during radiation work.

Evaluation of Occupational, Facility and Environmental Radiological Data From the Centralized Radioactive Waste Management Facility in Accra, Ghana

  • Gustav Gbeddy;Yaw Adjei-Kyereme;Eric T. Glover;Eric Akortia;Paul Essel;Abdallah M.A. Dawood;Evans Ameho;Emmanuel Aberikae
    • 방사성폐기물학회지
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    • 제21권3호
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    • pp.371-381
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    • 2023
  • Evaluating the effectiveness of the radiation protection measures deployed at the Centralized Radioactive Waste Management Facility in Ghana is pivotal to guaranteeing the safety of personnel, public and the environment, thus the need for this study. RadiagemTM 2000 was used in measuring the dose rate of the facility whilst the personal radiation exposure of the personnel from 2011 to 2022 was measured from the thermoluminescent dosimeter badges using Harshaw 6600 Plus Automated TLD Reader. The decay store containing scrap metals from dismantled disused sealed radioactive sources (DSRS), and low-level wastes measured the highest dose rate of 1.06 ± 0.92 µSv·h-1. The range of the mean annual average personnel dose equivalent is 0.41-2.07 mSv. The annual effective doses are below the ICRP limit of 20 mSv. From the multivariate principal component analysis biplot, all the personal dose equivalent formed a cluster, and the cluster is mostly influenced by the radiological data from the outer wall surface of the facility where no DSRS are stored. The personal dose equivalents are not primarily due to the radiation exposures of staff during operations with DSRS at the facility but can be attributed to environmental radiation, thus the current radiation protection measures at the Facility can be deemed as effective.

PRIMORDIAL RADIONUCLIDES DISTRIBUTION AND DOSE EVALUATION IN UDAGAMANDALAM REGION OF NILGIRIS IN INDIA

  • Manikandan, N.Muguntha;Selvasekarapandian, S.;Sivakumar, R.;Meenakshisundaram, V.;Raghunath, V.M.
    • Journal of Radiation Protection and Research
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    • 제26권3호
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    • pp.183-190
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    • 2001
  • The activity concentration of primordial radionuclides i.e., $^{238}U$ series, $^{232}Th$ series and $^{40}K$, in soil samples collected from Udagamandalam environment, have been measured by employing NaI (Tl) Gamma ray Spectrometer. The absorbed gamma dose rate has also been simultaneously measured by using both Environmental Radiation Dosimeter at each soil sampling location (ambient gamma dose) as well as from the gamma dose derived from the activity concentration of the primordial radionuclides. The results of activity concentration of each radio nuclides in soil, absorbed dose rate in air due to soil activity and possible cosmic radiation at each location along with human effective dose equivalent for Udagamandalam environment are presented and discussed.

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Analysis of radioactivity levels and hazard assessment of black sand samples from Rashid area, Egypt

  • Abdel-Rahman, Mohamed A.E.;El-Mongy, Sayed A.
    • Nuclear Engineering and Technology
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    • 제49권8호
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    • pp.1752-1757
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    • 2017
  • The aim of this study is to evaluate the radioactivity levels and radiological impacts of representative black sand samples collected from different locations in the Rashid area, Egypt. These samples were prepared and then analyzed using the high-resolution gamma ray spectroscopy technique with a high-purity germanium detector. The activity concentration ($A_c$), minimum detectable activity, absorbed gamma dose rate, external hazard index ($H_{ex}$), annual effective dose rate equivalent, radium equivalent, as well as external and internal hazard index ($H_{ex}$ and $H_{in}$, respectively) were estimated based on the measured radionuclide concentration of the $^{238}U$($^{226}Ra$) and $^{232}Th$ decay chains and $^{40}K$. The activity concentrations of the $^{238}U$, $^{232}Th$ decay series and $^{40}K$ of these samples varied from $45.11{\pm}3.1Bq/kg$ to $252.38{\pm}34.3Bq/kg$, from $64.65{\pm}6.1Bq/kg$ to $579.84{\pm}53.1Bq/kg$, and from $403.36{\pm}20.8Bq/kg$ to $527.47{\pm}23.1Bq/kg$, respectively. The activity concentration of $^{232}Th$ in Sample 1 has the highest value compared to the other samples; this value is also higher than the worldwide mean range as reported by UNSCEAR 2000. The total absorbed gamma dose rate and the annual effective dose for these samples were found to vary from 81.19 nGy/h to 497.81 nGy/h and from $99.86{\mu}Sv/y$ to $612.31{\mu}Sv/y$, which are higher than the world average values of 59 nGy/h and $70{\mu}Sv/y$, respectively. The $H_{ex}$ values were also calculated to be 3.02, 0.47, 0.63, 0.87, 0.87, 0.51 and 0.91. It was found that the calculated value of $H_{ex}$ for Sample 1 is significantly higher than the international acceptable limit of <1. The results are tabulated, depicted, and discussed within national and international frameworks, levels, and approaches.

실내 $^{222}Rn$$^{222}Rn$ 딸핵종에 의한 피폭선량 해석연구 (Study on the Assessment of Dose Equivalent due to the Inhalation of $^{222}Rn$ and Its Daughters in Indoor Air)

  • 전재식;채하석;이철영;조혁;하정우
    • Journal of Radiation Protection and Research
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    • 제20권1호
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    • pp.16-24
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    • 1995
  • 활성탄 캐니스터법과 알파분광분석 법을 이용하여 실내 공기중의 $^{222}Rn$ 및 그 딸핵종의 농도와 $^{222}Rn$과 그 딸핵종 사이의 평형인자를 동시에 측정하였다. 실내 체재율을 0.8, 일반인과 작업종사자의 호흡율을 각각 $0.75m^3\;h^{-1}$$1.2m^3\;h^{-1}$로 가정하고, 실내 공기중의 $^{222}Rn$과 그 딸핵종의 흡입에 의한 부위별 폐선량을 세가지 모형 즉, Jacobi-Eisfeld, James-Birchall 및 ICRP 모형으로 평가하고 연간총유효선량을 평가하였다.

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심장 전기생리학 검사 시 조건 변화에 따른 환자 피폭 선량 평가 (Evaluation of Patient Exposure Dose during Cardiac Electrophysiology Study under Various Conditions)

  • 고성빈;안성민
    • 대한방사선기술학회지:방사선기술과학
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    • 제46권6호
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    • pp.501-508
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    • 2023
  • This study used a adult absorption dose phantom (CIRS model 701-G, USA) made of human equivalent material and the vascular imaging equipment Allura Xper FD 20 (Philips, Netherlands). Optically stimulated luminescent dosimeters (OSLD) were inserted into the anatomical positions corresponding to each organ, and the exposure dose was measured. Dose area product (DAP) and air kerma (AK) measured by the dose meter in the equipment were compared. Continuous imaging was performed at two angles for a total of 20 minutes, with a frame per seconds of 3.75 and 7.5 fps and an FOV of 42 cm, 37 cm, and 31 cm, respectively, under the conditions of fluoflavor I, II, and III, each selected for 5 repetitions. This study was found that selecting a lower fps was the most effective way to reduce patient exposure dose, and adjusting the fluoflavor was a good alternative method for reducing patient exposure dose at high fps. Therefore the method of condition change with the greatest dose reduction effect is to set the minimum FPS and can reduce patient exposure dose according to geometric conditions and fluoflavor characteristics.