• 제목/요약/키워드: Dose Rate

검색결과 3,201건 처리시간 0.039초

Comparison of Dose Rates from Four Surveys around the Fukushima Daiichi Nuclear Power Plant for Location Factor Evaluation

  • Sanada, Yukihisa;Ishida, Mutsushi;Yoshimura, Kazuya;Mikami, Satoshi
    • Journal of Radiation Protection and Research
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    • 제46권4호
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    • pp.184-193
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    • 2021
  • Background: The radionuclides released by the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident 9 years ago are still being monitored by various research teams and the Japanese government. Comparison of different surveys' results could help evaluate the exposure doses and the mechanism of radiocesium behavior in the urban environment in the area. In this study, we clarified the relationship between land use and temporal changes in the ambient dose rates (air dose rates) using big data. Materials and Methods: We set a series of 1 × 1 km2 meshes within the 80 km zone of the FDNPP to compare the different survey results. We then prepared an analysis dataset from all survey meshes to analyze the temporal change in the air dose rate. The selected meshes included data from all survey types (airborne, fixed point, backpack, and carborne) obtained through the all-time survey campaigns. Results and Discussion: The characteristics of each survey's results were then evaluated using this dataset, as they depended on the measurement object. The dataset analysis revealed that, for example, the results of the carborne survey were smaller than those of the other surveys because the field of view of the carborne survey was limited to paved roads. The location factor of different land uses was also evaluated considering the characteristics of the four survey methods. Nine years after the FDNPP accident, the location factor ranged from 0.26 to 0.49, while the half-life of the air dose rate ranged from 1.2 to 1.6. Conclusion: We found that the decreasing trend in the air dose rate of the FDNPP accident was similar to the results obtained after the Chernobyl accident. These parameters will be useful for the prediction of the future exposure dose at the post-accident.

선형가속기의 선량율에 따른 쐐기필터의 선량분포 (Dose Distribution of Wedge filter by Dose Rate in LINAC)

  • 권태형;김승욱;윤용학;원도연;정경환;정재은;조준호
    • 한국방사선학회논문지
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    • 제9권5호
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    • pp.323-329
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    • 2015
  • 이 연구는 금속쐐기필터를 대신하여 동적쐐기필터를 사용할 수 있을지에 대한 적정성 평가에 관한 것이다. 선형가속기에서 발생되는 엑스선 에너지는 6 MV, 10 MV로 상용화되어있다. 금속쐐기필터의 $15^{\circ}$, $30^{\circ}$, $45^{\circ}$, $60^{\circ}$에 각각 100, 200, 300, 400, 500, 600 선량율(MU/min)로 48번 조사하였고, 동적쐐기필터와의 비교를 위해 같은 조건으로 총 96번 조사하였다. 측정조건은 선원필름간 거리 100cm, 조사면 $10{\times}10cm$ 로 측정하였다. 현상된 필름을 스캔하여 선량분석프로그램으로 교정 후 분석하였고, 표준편차를 구해 선량율을 비교하였다. 동적쐐기필터는 선량, 산란선 및 치료시간을 감소시키며, 환자에 조사되는 선량이 적어 매우 유용하다. 동일한 조건에서 선량율에 따른 오차는 연관성이 없으므로 환자의 상황에 따라 고선량율의 치료를 사용하는 것도 가능할 것으로 생각된다.

감마선 조사가 감초(Glycyrrhiza uralensis)의 초기 생육 및 DNA 손상에 미치는 영향 (Effects of Gamma-ray Irradiation on Growth Characteristics and DNA Damage in Licorice (Glycyrrhiza uralensis))

  • 류재혁;임승빈;김동섭;안준우;김진백;김상훈;강시용
    • 방사선산업학회지
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    • 제8권2호
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    • pp.89-95
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    • 2014
  • This study was conducted to determine the optimal dose of gamma-ray on the growth and nucleus DNA damage for mutation breeding in licorice. Gamma-rays irradiated to dry seeds with various doses (0 to 1000 Gy). Significant decreases in germination rate (%), survival rate (%) and growth characteristics (plant height, number of leaves, root length and fresh weight) were observed by dose of increased. $LD_{50}$ (lethal dose) was approximately 400 Gy to 500 Gy. Also, reduction doses ($RD_{50}$) of plant height, number of leaves, root length and flash weight were 428 Gy, 760 Gy, 363 Gy and 334 Gy, respectively. It is supplest that the optimal dose of gamma irradiation for licorice mutation induction might be about 400 Gy in this study. We also conducted comet assay to observe nucleus DNA damage due to gamma irradiation. In comet assay, a clear difference was identified over 300 Gy treatments. With increasing doses of gamma-ray in the range of 100 to 1000 Gy, the rate of head DNA was decreased significantly from 92.88% to 73.09%. Tail length(${\mu}m$) was increased as the dose of increased over 300 Gy. Growth characteristics (Germination rate, Survival rate, plant height, number of leaves, root length and fresh weight) were highly negatively ($P{\leq}0.01$) correlated with dose. While the tail length was highly positively ($P{\leq}0.01$) correlated with dose.

방사성요오드(I-131) 격리병실 치료 관리를 위한 환자의 체외방사선량률과 상주 보호자의 피폭선량평가 (Evaluation of Caregivers' Exposed Dose and Patients' External Dose Rate for Radioactive Iodine (I-131) Therapy Administration in Isolated Ward)

  • 강석진;이두현;소영;이정우
    • 대한방사선기술학회지:방사선기술과학
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    • 제45권4호
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    • pp.347-353
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    • 2022
  • In this study, the radiation dose rate was measured by time and distance and evaluated whether radiation dose rate was suitable for domestic and international discharge criteria. In addition, the radiation dose emitted from the patient was measured with a glass dosimeter to evaluate the exposure dose if the caregiver stays in the isolated ward by placing a humanoid phantom instead of the caregiver at a distance of 1 m from the patient, on the second day of treatment. After 23 hours of isolation, the radiation dose rates at a distance of 1 m were 20.54 ± 6.21 µSv/h at 2.96 GBq administration and 27.94 ± 12.33 µSv/h at 3.70 GBq administration. The radiation dose rates at a distance of 1 m were 25.90 ± 2.21 µSv/h when 2.96 GBq was administered and 34.22 ± 10.06 µSv/h when 3.70 GBq was administered after 18 hours of isolation. However, if the isolation period is short may cause unnecessary radiation exposure to the third person. The reading of the attached dosimeter from the morning of the second day of treatment until removal was 0.01 to 0.95 mSv, which is a surface dose determined by the International Commission on Radiation Units and Measurements. And the depth dose was 0.01 to 0.99 mSv. On the second day of treatment, even if the patient caregivers stayed in the isolation ward, the exposure dose of the patient family did not exceed the effective dose limit of 5 mSv recommended by the ICRP and NCRP.

정액의 희석배율 및 주입 정자수가 닭의 수정능력에 미치는 영향

  • 김학규;나재천;최철환;장병귀;상병돈;이상진
    • 한국가금학회:학술대회논문집
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    • 한국가금학회 2002년도 가을 학술발표논문집
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    • pp.116-117
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    • 2002
  • 보존온도별(5, 25, 35$^{\circ}C$)로 정액과 희석액의 비율(1:1, 1:2, 1:3)을 달리하여 보존시간(1, 3, 6시간)에 따른 정자운동성을 조사한바, 5$^{\circ}C$ 냉장 온도에서는 희석배율에 따른 보존시간별 정자운동성은 차이가 없었으나, $25^{\circ}C$ 상온에서 6시간, 35$^{\circ}C$ 고온에서 3시간 이상 보존할 때 정액과 희석액의 비율이 1:1보다는 1:2 비율에서 정자운동성이 현저히 높게 유지되었다(P<0.05). 온도가 높을수록 1:1 배율보다는 1:2 이상 희석배율을 높여 주었을 때 정자의 운동성을 높게 유지시킬 수 있었다. Skim milk glucose액을 사용하여 닭 정액을 희석한 후 인공수정 하였을 때, 1회 주입정자수를 0.2, 0.4, 1 및 2억으로 하였을 때 각각 90.67, 94.00, 96.00 및 98.67%의 수정율을 나타냈다. 90%이상의 수정율을 얻기 위해서는 0.2억 이상의 정자 주입이 필요하며, 94%이상 안정적인 수정율을 얻기 위해서는 0.4억의 정자가 필요하다고 판단된다.

토끼의 갑상선 측정 (Determination of Thyroid Secretion Rate in Rabbit)

  • 이종진;윤세중
    • 한국동물학회지
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    • 제3권1호
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    • pp.19-23
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    • 1960
  • A method for determination of thyroid secretion rate in rabbit by means of radioactive iodine presented. After injection of radioactive iodine, in vivo determination so f radioactivity in thyroid gland were made during a 19 day-experimental period. In the same period blood samples were drawn and analyzed for protein-bound iodine (PBI) and for protein-bound radioactive iodine(PBI181). A rate constant for secretion of thyroid hormone was calculated from the disappearance rate of radioactive iodine in thyroid gland. The secretion rate of radioactive hormone iodine was calculated by multiplying this rate constant by the amount of radioactive iodine present in thyroid gland. Assuming that the specific radioactiveness of the circulating thyroid hormone and of the hormone just secreted were identical , thyroid secretion rate was calculated by the equation. {{{{ { Secreted hormone-iodine , gamma /hr} over { Secreted hormone-I^131, % dose/hr }= { PBI, ${\gamma}$/ml.Serum} over { PBI^131 , % dose/ml . Serum } }} The method presented consisted of measurements for series of independent criteria on thyroid function, and the resulting thyroid secretion rate was calculated by combination of those.

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다중 그룹 상황에서의 최소 효과 용량을 정하는 비모수적 검정법 (Nonparametric Procedures for Finding the Minimum Effective Dose in Each of Several Group)

  • 배수현;김동재
    • Communications for Statistical Applications and Methods
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    • 제19권1호
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    • pp.33-45
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    • 2012
  • 신약 개발 연구 또는 임상시험에서 개발된 약이 0용량 대조군과 비교해 효과 차이가 있는 가장 작은 용량을 최소 효과 용량(MED)이라 한다. 본 논문에서는 다중 그룹 상황에서 동시적(simultaneous)으로 각 각 그룹의 최소 효과 용량을 확인하기 위하여 위치(placement)에 기초한 비모수적 방법을 제시하였다. 또한 Monte Carlo 모의실험을 통하여 기존에 제시된 검정법과 본 논문에서 제안한 검정법의 검정력(power)과 FWE(Family-wise Error Rate)를비교하였다.

Real-time monitoring of ultra-high dose rate electron beams using bremsstrahlung photons

  • Hyun Kim;Dong Hyeok Jeong;Sang Koo Kang;Manwoo Lee;Heuijin Lim;Sang Jin Lee;Kyoung Won Jang
    • Nuclear Engineering and Technology
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    • 제55권9호
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    • pp.3417-3422
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    • 2023
  • Recently, as the clinically positive biological effects of ultra-high dose rate (UHDR) radiation beams have been revealed, interest in flash radiation therapy has increased. Generally, FLASH preclinical experiments are performed using UHDR electron beams generated by linear accelerators. Real-time monitoring of UHDR beams is required to deliver the correct dose to a sample. However, it is difficult to use typical transmission-type ionization chambers for primary beam monitoring because there is no suitable electrometer capable of reading high pulsed currents, and collection efficiency is drastically reduced in pulsed radiation beams with ultra-high doses. In this study, a monitoring method using bremsstrahlung photons generated by irradiation devices and a water phantom was proposed. Charges collected in an ionization chamber located at the back of a water phantom were analyzed using the bremsstrahlung tail on electron depth dose curves obtained using radiochromic films. The dose conversion factor for converting a monitored charge into a delivered dose was determined analytically for the Advanced Markus® chamber and compared with experimentally determined values. It is anticipated that the method proposed in this study can be useful for monitoring sample doses in UHDR electron beam irradiation.

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

  • 윤홍주;이용기;이인자
    • 대한방사선기술학회지:방사선기술과학
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    • 제42권6호
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    • pp.477-482
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    • 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.

BENCHMARK CALCULATION OF CANDU END SHIELDING SYSTEM

  • Gyuhong Roh;Park, Hangbok
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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    • pp.618-623
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    • 1998
  • A shielding analysis was performed for the end shield of CANDU 6 reactor. The one-dimensional discrete ordinate code ANISN with a 38-group neutron-gamma library, extracted from DLC-37D library, was used to estimate the dose rate for the natural uranium CANDU reactor. For comparison MCNP-4B calculation was performed for the same system using continuous, discrete and multi-group libraries. The comparison has shown that the total dose rate of the ANISN calculation agrees well with that of the MCNP calculation. However, the individual dose rate (neutron and gamma) has shown opposite trends between AMISN and MCNP estimates, which may require a consistent library generation for both codes.

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