• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1991-1997
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• 2019

In this manuscript, we present a method for the direct calculation of an ambient dose equivalent (H^* (10)) for the external gamma-ray exposure with an energy range of 40 keV to 2 MeV in an electronic personal dosimeter (EPD). The designed EPD consists of a 3 × 3 ㎟ PIN diode coupled to a 3 × 3 × 3 ㎣ CsI (Tl) scintillator block. The spectrum-to-dose conversion function (G(E)) for estimating H^* (10) was calculated by applying the gradient-descent method based on the Monte-Carlo simulation. The optimal parameters for the G(E) were found and this conversion of the H^* (10) from the gamma spectra was verified by using ²⁴¹Am, ¹³⁷Cs, ²²Na, ⁵⁴Mn, and ⁶⁰Co radioisotopes. Furthermore, gamma spectra and H^* (10) were obtained for an arbitrarily mixed multiple isotope case through Monte-Carlo simulation in order to expand the verification to more general cases. The H^* (10) based on the G(E) function for the gamma spectra was then compared with H^* (10) calculated by simulation. The relative difference of H^* (10) from various single-source spectra was in the range of ±2.89%, and the relative difference of H^* (10) for a multiple isotope case was in the range of ±5.56%.

• Nuclear Engineering and Technology
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• 제6권4호
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• pp.239-247
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• 1974

방사선 안전관리의 효과적인 연구를 위해 유사인체 모형을 설계, 제작하였다. 이 모형의 치수는 한국인의 체격과 근사하게 맞추었으며 두께 2.5cm인 포리에칠렌판 35매로 구성되었다. 유사인체모형의 표면에 착용한 열형광 설량계(Disc type TLD)로써 외부 ${\gamma}$-방사선에 의한 신체특정부위의 피폭선량을 측정하였으며, 아울러 깊이에 따른 흡수선량에 대해서 열형광 선량계(micro rod type TLD)로써 측정하여 결정장기 부위의 각단면에 대한 등가선량선을 얻었다. 선량측정은 방사선 작업자의 작업환경조건에 유사하도록 유사인체 모형에 대해 배치하고 여러 입사방항에 대해서 실시하였다. 그 결과 Cs-137, ${\gamma}$-방사선에 대하여 두께 20cm인 유사인체 모형에서의 감쇄는 0.439였으며 이는 보고된 자료들과 잘 일치하였다.

• Bulletin of the Korean Chemical Society
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• 제33권7호
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• pp.2265-2268
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• 2012

Aqueous solution of oxygenated Direct yellow 12 dye has been evaluated spectrophotometrically as a possible gamma rays dosimeter. The neutral (pH-7), alkaline (pH-12.5) and acidic (pH-5.5) aqueous solution of the dye were prepared and exposed to various gamma doses. Absorption spectra of unirradiated and irradiated solutions were recorded at 400 nm peak. The increase in absorbance with the increase in irradiation dose was observed from 1 to 6 kGy. The stability response of the dye solution for different environmental conditions such as temperature (low & high), light and darkness were investigated during post irradiation storage for ten days. The dye solution showed high stability in darkness for the studied period. The optical density of the dye solution was found to be decreased at high temperature storage.

• 한국의학물리학회지:의학물리
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• 제24권3호
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• pp.140-144
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• 2013

본 연구에서는 방사선생물 분야에서는 사용하는 세슘-137 조사기에 대한 기준 흡수선량을 측정하고 시료의 방사선량 평가에 활용하기 위하여 유리선량계를 교정하였다. 세슘-137 감마선에 대하여 IAEA TRS-277 프로토콜을 적용하여 정밀하게 물흡수선량을 결정하였다. 기준 흡수선량 측정에는 PTW-TM300013 전리함과 PTW-TM41023 물팬텀을 사용하였으며, 유리선량계는 DoseAce사의 GD-302M 모델을 사용하였다. 교정된 유리선량계의 불확도(1 SD)는 약 2.7%로 평가되며, 본 결과는 연구용 시료의 방사선량 측정에 이용될 예정이다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1999년도 추계학술대회 논문집 학회본부 B
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• pp.754-756
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• 1999

In this paper, we have developed a high-sensitivity SNRD(Semiconductor Nuclear Radiation Detector) using silicon PIN photodiode. The SNRD is constructed with silicon PIN photodiode(S3590-05), preamplifier and shaping amplifier. To show the effectiveness of SNRD, nuclear radiation experiments are conducted with $\gamma$-ray Ba-133, Cs-137 and Co-60. The SNRD is different in characteristics of the energy spectrum to scintillation detectors. However, the SNRD have a good linearity on $\gamma$-ray energy and activity. The results of this paper can be applied to electronic personal dosimeter.

• 대한방사선기술학회지:방사선기술과학
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• 제43권5호
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• pp.375-382
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• 2020

PET/CT is a medical equipment that detects 0.511 MeV of gamma rays. The radiation workers are inevitably exposed to ionizing radiation in the process of handling the isotope. Accordingly, PET/CT workers use syringe shields made of lead and tungsten to protect their hands. However, lead and tungsten are known to generate very high scattering particles by interacting with gamma rays. Therefore, in this study, we tried to find out the effect on the scattering particles emitted from the syringe shield. In the experiment, first, the exposure dose to the hand (Rod phantom) was evaluated according to the metal material (lead, tungsten, iron, stainless steel) using Monte Carlo simulation. The exposure dose was compared according to whether or not plastic is attached. Second, the exposure dose of scattering particles was measured using a dosimeter and lead. As a result of the experiment, the shielding rate of plastics using the Monte Carlo simulation showed the largest difference in dose of about 40 % in lead, and the lowest in iron, about 15 %. As a result of the dosimeter test, when the plastic tape was wound on lead, it was found that the reduction rate was about 15 %, 28 %, and 39 % depending on the thickness. Based on the above results, it was found that 0.511 MeV of gamma ray interacts with the shielding tool to emit scattered rays and has a very large effect on radiation exposure. However, it was considered that the scattering particles could be sufficiently removed with plastics with a low atomic number. From now on, when using high-energy radiation, the shielding tool and the skin should not be in direct contact, and should be covered with a material with a low atomic number.

• Journal of Radiation Protection and Research
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• 제9권1호
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• pp.3-10
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• 1984

The properties of $Al_2O_3$ thermoluminescent phosphor have been observed to apply for gamma dosimetry in vivo. Glow peaks at 380, 420, 490 kelvin temperature with emission in the blue region have been detected and calculated as 1.4 eV the activation energy by means of heat response rising time method. Sensitization and supralinearity in $Al_2O_3$ phosphor could be consistently explained by the deep trap model. Studies of the thermoluminescence growth rate with gamma ray exposure showed linearly to $10^4$ Roentgen and then supralinear rate detected 1.2 power of exposure dose sensitization of $Al_2O_3$ is described five times more than TLD-100 and the fading time is shorter and then tried to apply for gamma dosimetry in vivo.

• 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.

• Journal of Radiation Protection and Research
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• 제11권1호
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• pp.57-64
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• 1986

우라늄, 플루토늄 및 그 자핵종(子核種)으로부터 방출(放出)되는 저(低)에너지감마선(線) 또는 저(低)에너지영역(領域)의 X-선(線)스펙트럼으로부터의 필름배지 개인피폭선량해석(個人被曝線量解析) 및 평가(評價)에 필요(必要)한 기술자료(技術資料)를 제공(提供)하였다. 필름배지는 한국핵연료개발공단(韓國核燃料開發公團)(현(現) 한국(韓國)에너지연구소(硏究所))에서 개발(開發)한 것이며, 저(低)에너지표준선원(標準線源)은 방사선량강도(放射線量强度)의 손실(損失)을 최소(最少)로 유지(維持)하면서 가능(可能)한 한 X-선(線)스펙트럼폭(幅)을 금속(金屬)필터로 좁게 줄인 X-선(線)을 이용(利用)하였다. 그 결과(結果) 얻은 X-선(線)에너지는 49 keV, 154 keV 및 256 keV 이었으며, 이 값은 Kramer의 이론적계산결과(理論的計算結果)와 잘 일치(一致)하였다. 이들 에너지 군별(群別) X-선(線)의 필름광학밀도(光學密度)와 선량(線量)과의 관계(關係)는 Matrix 법(法)으로 해석(解析)하여 측정광학밀도(測定光學密度)로부터 저(低)에너지 X-선(線)의 개인피폭선량(個人被曝線量)을 직접(直接) 환산(換算)할 수 있게 되었다. 이 결과(結果)는 국내(國內) 방사선작업(放射線作業) 종사자(從事者)들의 개인피폭선량측정자료(個人被曝線量測定資料)의 균질성(均質性) 향상(向上)에 기여(寄與)하게 될 것이다.

• Nuclear Engineering and Technology
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• 제7권4호
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• pp.285-293
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• 1975

30cm 직경 포리에티렌 구체내의 길이에 따른 선량분포중 최대흡수선량인 흡수선량지수를 주어진 감마방사선장내에서 열형광선량계를 이용하여 결정하였다. 열형광선량계내의 흡수선량과 주위 눈질내의 흡수선량간의 환산은 Burlin의 general cavity theory에 의거하였다. $^{60}$Co과 $^{137}$Cs에 의한 방사선장에서 구체내 최대흡수선량은 구체표면으로 부터 각각 0.5cm 및 0.3cm에 나타났으며 이 결과는 이론적으로 예상한 분포특성과 아주 근사하였다.