• Journal of Radiation Protection and Research
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• 제47권2호
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• pp.77-85
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• 2022

Background: After the Fukushima Daiichi Nuclear Power Station (FDNPS) accident, a model was developed to estimate the external exposure doses for residents who were expected to return to their homes after evacuation orders were lifted. However, the model's accuracy and uncertainties in parameters used to estimate external doses have not been evaluated. Materials and Methods: The model estimates effective doses based on the integrated ambient dose equivalent (H^*(10)) and life patterns, considering a dose reduction factor to estimate the indoor H^*(10) and a conversion factor from H^*(10) to the effective dose. Because personal dose equivalent (H_p(10)) has been reported to agree well with the effective dose after the FDNPS accident, this study validates the model's accuracy by comparing the estimated effective doses with H_p(10). The H_p(10) and life pattern data were collected for 36 adult participants who lived or worked near the FDNPS in 2019. Results and Discussion: The estimated effective doses correlated significantly with H_p(10); however, the estimated effective doses were lower than H_p(10) for indoor sites. A comparison with the measured indoor H^*(10) showed that the estimated indoor H^*(10) was not underestimated. However, the H_p(10) to H^*(10) ratio indoors, which corresponds to the practical conversion factor from H^*(10) to the effective dose, was significantly larger than the same ratio outdoors, meaning that the conversion factor of 0.6 is not appropriate for indoors due to the changes in irradiation geometry and gamma spectra. This could have led to a lower effective dose than H_p(10). Conclusion: The estimated effective doses correlated significantly with H_p(10), demonstrating the model's applicability for effective dose estimation. However, the lower value of the effective dose indoors could be because the conversion factor did not reflect the actual environment.

• 한국의학물리학회지:의학물리
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• 제32권4호
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• pp.145-152
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• 2021

Purpose: During the treatments of cancer patients with a linear accelerator (LINAC) using photon beams with energies ≥8 MV, the components inside the LINAC head get activated through the interaction of photonuclear reaction (γ, n) and neutron capture (n, γ). We used spectroscopy and measured the dose rate for the LINAC in operation after the treatment ended. Methods: We performed spectroscopy and dose rate measurements for three units of LINACs with a portable high-purity Germanium (HPGe) detector and a survey meter. The spectra were obtained after the beams were turned off. Spectroscopy was conducted for 3,600 seconds, and the dose rate was measured three times. We identified the radionuclides for each LINAC. Results: According to gamma spectroscopy results, most of the nuclides were short-lived radionuclides with half-lives of 100 days, except for ⁶⁰Co, ⁶⁵Zn, and ¹⁸¹W nuclides. The dose rate for three LINACs obtained immediately in front of the crosshair was in the range of 0.113 to 0.129 µSv/h. The maximum and minimum dose rates measured on weekends were 0.097 µSv/h and 0.092 µSv/h, respectively. Compared with the differences in weekday data, there was no significant difference between the data measured on Saturday and Sunday. Conclusions: Most of the detected radionuclides had half-lives <100 days, and the dose rate decreased rapidly. For equipment that primarily used energies ≤10 MV, when the equipment was transferred after at least 10 minutes after shutting it down, it is expected that there will be little effect on the workers' exposure.

• 한국압력기기공학회 논문집
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• 제18권2호
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• pp.43-49
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• 2022

The purpose of this study is to evaluate the radiation effect on damage when the external shield of the spent nuclear fuel transport cask is damaged due to impact as the cause of an unexpected accident. The neutron and gamma-ray intensities and spectra are calculated using the ORIGEN-Arp module in the SCALE 6.2.4 code package⁽¹⁾ and then using MCNP6.2⁽²⁾ code calculate the dose rate. In order to evaluate the radiation dose according to the size of damage caused by external impact, various sized holes of 0.3~13.7% are assumed in the outer shield of the cask to evaluate the sensitivity to the dose. In the case of radiation source leakage, damage to the nuclear fuel assembly is assumed to be up to 6% based on overseas test cases. When only the outer shield is damaged, the maximum surface dose is calculated as 3.12E+03 mSv/hr. However, if the radiation source is leaked due to damage to the nuclear fuel assembly, it becomes 7.00E+05 mSv/hr which is about 200 times greater than the former case.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2258-2265
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• 2024

The present investigation aims to study the role of Pr₂O₃ on the structural, physical, and radiation shielding properties of a dense cadmium lead borate glass. The XRD was used to affirm the glassy amorphous structure of fabricated sample materials. Moreover, the FTIR was used to record the change in the FT-IR spectra due to the addition of Pr₂O₃ in the wavenumber interval between 400 and 4000 cm^-1. The features of glass surfaces and the elemental analyses for the synthesized Pr₂O₃-reinforced cadmium lead borate glasses were performed using a SEM, supported by an energy-dispersive spectrometer. The γ-ray protection capacity was evaluated using the Monte Carlo method in a wide energy interval ranging between 0.015 and 15 MeV. The linear attenuation coefficient (LAC) at 1 MeV was reduced by a factor of 10 % from 0.372 cm^-1 to 0.340 cm^-1. The decrease in the LAC values negatively affected the other shielding properties such as half-value thickness and the transmission factor. Although the linear attenuation coefficient is decreased slightly with the partial substitution of CdO by Pr₂O₃ compound, the fabricated glass samples still have a high shielding capacity compared to the traditional commercial glasses as well as previous similar reported glasses.

• 한국결정성장학회지
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• 제23권6호
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• pp.283-290
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• 2013

수평 전기로에서 $MgGa_2Se_4$ 다결정을 합성하여 HWE(Hot Wall Epitaxy)방법으로 $MgGa_2Se_4$ 단결정 박막을 반절연성 GaAs(100)기판에 성장시켰다. $MgGa_2Se_4$단결정 박막의 성장 조건은 증발원의 온도 $610^{\circ}C$, 기판의 온도 $400^{\circ}C$였고 성장 속도는 $0.5{\mu}m/hr$였다. 이때 이중결정 X-선 요동곡선(DCRC)의 반폭치(FWHM)도 212 arcsec로 가장 작아 최적 성장 조건임을 알 수 있었다. $MgGa_2Se_4$/SI(Semi-Insulated) GaAs(100) 단결정 박막의 광흡수와 광전류 spectra를 293 K에서 10 K까지 측정하였다. 광흡수 스펙트럼으로부터 band gap Eg(T)는 varshni공식에 따라 계산한 결과 $E_g(T)=2.34 eV-(8.81{\times}10^{-4}eV/K)T^2/(T+251K)$이었으며 광전류 스펙트럼으로부터 Hamilton matrix(Hopfield quasicubic mode)법으로 계산한 결과 crystal field splitting energy ${\Delta}cr$값이 190.6 meV이며 spin-orbit energy ${\Delta}so$값은 118.8 meV임을 확인하였다. 10 K일 때 광전류 봉우리들은 n = 1, 27일때 $A_{1^-}$, $B_{1^-}$와 $C_{27}-exciton$ 봉우리임을 알았다.

• 한국결정성장학회지
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• 제18권5호
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• pp.217-224
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• 2008

수평 전기로에서 $ZnIn_2Se_4$ 단결정을 합성하여 HWE(Hot Wall Epitaxy)방법으로 $ZnIn_2Se_4$ 단결정 박막을 반절연성 GaAs(100) 기판에 성장시켰다. $ZnIn_2Se_4$ 단결정 박막의 성장 조건을 증발원의 온도 $630^{\circ}C$, 기판의 온도 $400^{\circ}C$였고 성장 속도는 0.5 $\mu m/hr$였다. $ZnIn_2Se_4$ 단결정 박막의 결정성의 조사에서 10K에서 광발광(photoluminescence) 스펙트럼이 682.7nm ($1.816{\underline{1}}eV$)에서 exciton emission 스펙트럼이 가장 강하게 나타났으며, 또한 이중결정 X-선 요통곡선(DCRC)의 반폭치(FWHM)도 128 arcsec로 가장 작아 최적 성장 조건임을 알 수 있었다. Hall 효과는 van der Pauw 방법에 의해 측정되었으며, 온도에 의존하는 운반자 농노와 이동도는 293 K에서 각각 $9.41\times10^{16}/cm^{-3}$, $292cm^2/V{\cdot}s$였다. $ZnIn_2Se_4$/SI(Semi-Insulated) GaAs(100) 단결정 박막의 광흡수와 광전류 spectra를 293 K에서 10K까지 측정하였다. 광흡수 스펙트럼으로부터 band gap $E_g(T)$는 varshni공식에 따라 계산한 결과 $E_g(T)=1.8622\;eV-(5.23\times10^{-4}eV/K)T^2/(T+775.5K)$ 이었으며 광전류 스펙트럼으로부터 Hamilton matrix(Hopfield quasicubic mode)법으로 계산한 결과 crystal field splitting energy ${\Delta}cr$값이 182.7meV이며 spin-orbit energy ${\Delta} so$값은 42.6meV임을 확인하였다. 10 K일 때 광전류 봉우리들은 n= 1, 27일때 $A_{1}-$, $B_{1}-$와 $C_{27}-exciton$ 봉우리임을 알았다.

• 센서학회지
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• 제11권5호
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• pp.309-318
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• 2002

수평 전기로에서 $CdIn_2S_4$ 다결정을 합성하여 HWE(Hot Wall Epitaxy)방법으로 $CdIn_2S_4$ 단결정 박막을 반절연성 GaAs (100)기판에 성장시켰다. $CdIn_2S_4$ 단결정 박막의 성장 조건은 증발원의 온도 $630^{\circ}C$, 기판의 온도 $420^{\circ}C$였고 성장 속도는 $0.5\;{\mu}m/hr$였다. $CdIn_2S_4$ 단결정 박막의 결정성의 조사에서 10 K에서 광발광(photoluminescence) 스펙트럼이 463.9 nm (2.6726 eV)에서 exciton emission 스펙트럼이 가장 강하게 나타났으며, 또한 이중 결정 X-선 요동 곡선(DCRC)의 반폭치(FWHM)도 127 arcsec로 가장 작아 최적 성장 조건임을 알 수 있었다. Hall 효과는 van der Pauw 방법에 의해 측정되었으며, 온도에 의존하는 운반자 농도와 이동도는 293K에서 각각 $9.01{\times}10^{16}/cm^3$, $219\;cm^2/V{\cdot}s$였다. $CdIn_2S_4$/SI(Semi-Insulated) GaAs(100) 단결정 박막의 광흡수와 광전류 spectra를 293K에서 10K까지 측정하였다. 광흡수 스펙트럼으로부터 band gap $E_g(T)$는 Varshni 공식에 따라 계산한 결과 $2.7116eV-(7.74{\times}10^{-4}eV/K)T^2$/(T+434K)이었으며 광전류 스펙트럼으로부터 Hamilton matrix(Hopfield quasicubic mode)법으로 계산한 결과 crystal field splitting ${\Delta}cr$값이 0.1291 eV이며 spin-orbit ${\Delta}so$값은 0.0248 eV임을 확인하였다. 10K일 때 광전류 봉우리들은 n = 1일때 $A_1$-, $B_1$-와 $C_1$-exciton 봉우리임을 알았다.

• Journal of Radiation Protection and Research
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• 제10권2호
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• pp.96-108
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• 1985

감마선분광분석 및 열형광선량측정법에 의한 자연환경방사선의 선량해석에 관한 연구를 1984년 10월부터 약 1년간에 걸쳐 충남대학교 대덕캠퍼스내의 1만 $m^2$ 규모의 평면개활지에서 수행하였다. 이 연구에서 사용한 검출기는 3'${\phi}{\times}$3' NaI(T1) 섬광계수기(閃光計數器)와 plastic 에 밀봉하여 금속판에 압착 처리한 chip 과 Teflon-disk 로된 2종의 LiF TLD 였다. 실측실험으로는 3회에 걸친 24시간 cycle의 in-situ spectrometry 와 2회의 3개월 cycle 과 1회의 1개월 cycle에 걸친 TLD field dosimetry를 수행하였다. 측정한 모든 spectrum은 G(E)연산자법에 의하여 조사선량율(照射線量率)로 환산하였고 그 결과로부터 환경 방사선의 지설성분(地設成分)을 산출하였다. 결과(結果)에 의하면 spectrometry로 구한 조사선량율이 평균 $(10.54{\pm}2.96){\mu}R/hr$, TLD chip으로 측정해석한 값은 $(12.0{\pm}3.4){\mu}R/hr$, disk에서 얻은 값이 $(11.0{\pm}3.6){\mu}R/hr$로 오차범위 안에서 매우 좋은 일치를 보이고 있다. 그러나 감마선분광분석에 의한 자연방사선의 일변화(日變化)에는 가끔 심한동요가 관측되었다. 정확한 환경방사선량해석을 위하여 감마선분광분석과 TLD의 적절한 동시 배합사용이 바람직 하며, 보다 고감도의 TLD에 관한 연구와 국제비교등을 통한 선량평가의 정도향상(精度向上)을 위한 보다 깊이 있는 연구가 필요하다는 결론(結論)에 도달하였다.

• 천문학회지
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• 제38권2호
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• pp.283-287
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• 2005

The slow evolution of global magnetic fields and other dynamical processes in atmospheres of CP magnetic stars lead to the development of induced electric currents in all conductive atmospheric layers. The Lorentz force, which results from the interaction between a magnetic field and the induced currents, may modify the atmospheric structure and provide insight into the formation and evolution of stellar magnetic fields. This modification of the pressure-temperature structure influences the formation of absorption spectral features producing characteristic rotational variability of some spectral lines, especially the Balmer lines (Valyavin et al., 2004 and references therein). In order to study these theoretical predictions we began systematic spectroscopic survey of Balmer line variability in spectra of brightest CP magnetic stars. Here we present the first results of the program. A0p star $\Theta$ Aur revealed significant variability of the Balmer profiles during the star's rotation. Character of this variablity corresponds to that classified by Kroll (1989) as a result of an impact of significant Lorentz force. From the obtained data we estimate that amplitudes of the variation at H$\alpha$, H$\beta$, H$\gamma$ and H$\delta$ profiles reach up to $2.4\%$during full rotation cycle of the star. Using computation of our model atmospheres (Valyavin et al., 2004) we interpret these data within the framework of the simplest model of the evolution of global magnetic fields in chemically peculiar stars. Assuming that the field is represented by a dipole, we estimate the characteristic e.m.f. induced by the field decay electric current (and the Lorentz force as the result) on the order of $E {\~} 10^{-11}$ cgs units, which may indicate very fast (< < $10^{10}$ years) evolution rate of the field. This result strongly contradicts the theoretical point of view that global stellar magnetic fields of CP stars are fossil and their the characteristic decay time of about $10^{10}$ yr. Alternatively, we briefly discuss concurring effects (like the ambipolar diffusion) which may also lead to significant atmospheric currents producing the observable Lorentz force.

• 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.