• Journal of Radiation Protection and Research
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• 제43권2호
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• pp.75-84
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• 2018

Background: Gamma-ray spectrometry helps in radiation shielding problems and different applications of radioisotopes. Experimental arrangements including broad beam geometries are widely used. The aim is to investigate and evaluate the ${\gamma}-ray$ spectra via attenuation by environmental materials. Materials and Methods: The photo peak to nominated parts in the ${\gamma}-ray$ spectra and the attenuation coefficients ${\mu}_b/{\rho}$ from broad beam geometries are measured for the materials water, soil, sand and cement at the energies 0.662, 1.25, and 1.332 MeV with a $3{^{\prime}^{\prime}}{\times}3{^{\prime}^{\prime}}$ NaI(Tl) detector. Results and Discussion: The ${\gamma}-ray$ spectra vary according to changes in the effective atomic number $Z_{eff}$ of the attenuator, the photon energy and the solid angle. The peak to total ratios are the most sensitive parts to variations in the experimental conditions and overturn in the region 0.663 MeV to 1.332 MeV. This is indicated as inversion trend. The results are discussed in view of $Z_{eff}$ and the experimental conditions. The intensity build-up is larger at the lower energy and larger scattering angles in agreement with Klein-Nishina formula and other results. The build-up factor B is$${\sim_=}$$1 at high ${\gamma}-energies$ and small scattering angles. Conclusion: The sensitivity to material characteristics decrease gradually from peak: to total, to Compton valley, to Compton plateau ratios. Rigorous collimation is necessary at small energies. Cement, of the largest $Z_{eff}$, is characterized by the maximum broad beam mass attenuation coefficients ${\mu}_b/{\rho}$. The obtained results provide information to decide for the suitable experimental set-up based on aim of the work.

• Journal of Radiation Protection and Research
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• 제30권4호
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• pp.167-174
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• 2005

The concentrations of natural and artificial radionuclides in soil and gamma ray dose rate in air at 233 locations in Korea have been determined. The national mean concentrations of $^{232}Th,\;^{226}Ra,\;^{40}K,\;^{137}Cs\;and\;^{90}Sr$ in soil were $60{\pm}31,\;33{\pm}14,\;673{\pm}238,\;35{\pm}9.3\;and\;5.0{\pm}3.4\;Bq\;kg^{-1}$, respectively. The mean gamma-ray dose rate at 1 m above the ground was $7918\;nGy\;h^{-1}$. $^{137}Cs$ concentration had highly significant correlation with organic matter content and cation exchange capacity. $^{90}Sr$ concentration had slightly coherent with pH. The results have been compared with other global radioactivity and radiation measurements.

• Journal of Radiation Protection and Research
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• 제36권4호
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• pp.174-182
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• 2011

With the reactor operation conditions - 4.3 wt% $^{235}U$ initial enrichment, burn-up 55,000 MWd/MTU, average power 34 MW/MTU for three periods burned time for 539.2 days per period and cooling time for 100 hours after shut down, to set up the condition to determine the minimum height (depth) of spent fuel storage pool to shut off the radiation out of the spent fuel storage pool and to store spent fuels safely, the dose rate on the specific position directed to the surface of spent fuel storage pool induced by the neutron and gamma-ray from spent fuels are evaluated. The length of spent fuel is 381 cm, and as the result of evaluation on each position from the top of spent fuel to the surface of spent fuel storage pool, it is difficult for neutrons from spent fuels to pass through the water layer of maximum 219 cm (600 cm from the floor of spent fuel storage pool) and 419 cm (800 cm from the floor of spent fuel storage pool) for gamma-ray. Therefore, neutron and gamma-ray from spent fuels can pass through below 419 cm (800 cm from the floor) water layer directed to the surface of spent fuel storage pool.

• Journal of Radiation Protection and Research
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• 제16권2호
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• pp.1-6
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• 1991

상온에서 사용할 수 있는 감마선 검출 소자로서 $HgI_2$ 소자의 응용성을 판단하기 위하여 기상 성장법으로 $HgI_2$ 단결정을 성장시켰고 이를 이용하여 검출 소자를 제작한 후 감마선 검출 특성을 조사하였다 성장된 단결정의 비저항과 전하 운반자 포획 밀도는 상온에서 각각 $10^{11}{\Omega}\;cm$와 $1.8{\times}10^{14}/cm^3$였으며 단결정의 Photoluminescence를 측정한 결과 성장된 $HgI_2$ 단결정의 밴드갭의 온도계수는 20K부터 77K에서 $-1.53{\times}10^{-4}eV/K$였다. 감마선 검출실험 결과 제작된 $HgI_2$ 검출 소자는 상온에서 우수한 계수 특성과 시간에 대한 선형적 축적 계수 특성을 나타내었으나 온도변화에 따라 계수의 특성의 변화는 심하였다.

• Journal of Radiation Protection and Research
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• 제9권1호
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• pp.11-18
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• 1984

Well type 전리함과 미세전류 측정희로를 사용하여 표준 감마선 전리함 장치를 개발하였다. 미세전류는 automatic Townsend balance with stepwise compensation방법을 사용하여 측정하였다. $^{226}Ra$을 기준 선원으로 택하여 감마 방출핵종인 $^{241}Am,\;^{133}Ba,\;^{60}Co,\;^{134}Cs,\;^{137}Cs^{22}Na$에 대한 비교 교정인자를 산출하였으며, 감마에너지의 함수로서 검출 효율 곡선을 구하였다.

• 전기학회논문지
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• 제62권10호
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• pp.1421-1424
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• 2013

The electronic equipment which is exposed to high level pulsed radiation is damaged by Upset, Latchup, and Burnout. Those damages come from the instantaneous photocurrent from electron-hole pairs generated in itself. Such damages appear as losses of a power in military weapon system or as a blackout in aerospace equipment and eventually caused in gross loss of national power. In this paper, we have implemented a RDC(Radiation detection and control module) as a part of the radiation protection technology of the electronic equipment or devices from the pulsed gamma radiation. The RDC, which is composed of pulsed gamma-ray detection sensor, signal processors, and pulse generator, is designed to protect the an important electronic circuits from the a pulse radiation. To verify the functionality of the RDC, LM118s, which had damaged by the pulse radiation, were tested. The test results showed that the test sample applied with the RDC was worked well in spite of the irradiation of a pulse radiation. Through the experiments we could confirm that the radiation protection technology implemented with the RDC had the functionality of radiation protection for the electronic devices.

• Journal of Radiation Protection and Research
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• 제42권1호
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• pp.26-32
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• 2017

Background: Ionizing radiation is known to be harmful to human health. The shielding of ionizing radiation depends on the attenuation which can be achieved by three main rules, i.e. time, distance and absorbing material. Materials and Methods: The mass attenuation coefficient, linear attenuation coefficient, Half Value Layer (HVL) and Tenth Value Layer (TVL) of X-rays (32 keV, 74 keV) and gamma rays (662 keV) are measured in Barium compounds. Results and Discussion: The measured values agree well with the theory. The effective atomic numbers ($Z_{eff}$) and electron density (Ne) of Barium compounds have been computed in the wide energy region 1 keV to 100 GeV using an accurate database of photon-interaction cross sections and the WinXCom program. Conclusion: The mass attenuation coefficient and linear attenuation coefficient for $BaCO_3$ is higher than the $BaCl_2$, $Ba(No_3)_2$ and BaSO4. HVL, TVL and mean free path are lower for $BaCO_3$ than the $BaCl_2$, $Ba(No_3)_2$ and $BaSO_4$. Among the studied barium compounds, $BaCO_3$ is best material for x-ray and gamma shielding.

• Journal of Radiation Protection and Research
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• 제34권4호
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• pp.170-175
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• 2009

감마선분광분석법을 이용하여 비상시 환경방사능 모니터링을 수행할 경우 스펙트럼 측정시 해당 시료의 종류에 따른 백그라운드 자료 확보와 이를 활용한 체계적인 핵종확인 과정이 선행되어야 한다. 비상시 환경방사능 모니터링을 고려하여 24시간 동안 포집 후 회화시킨 공기부유진 시료를 HPGe 감마선분광분석 시스템으로 계측하여 감마선에너지 스펙트럼을 얻었으며, 그 스펙트럼에서 보이는 피이크들의 핵종을 판별하기 위해 두 가지 방법 - 1) 반감기 추정 2) 핵자료를 이용한 축차우연동시합성피이크 확인 - 으로 접근하였다. 그 결과로서 공기부유진의 감마선에너지스펙트럼에 대한 핵종판별결과 자료를 산출하였다.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.3051-3058
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• 2022

In the present work, untreated Iraqi sand with grain sizes varied between 100 and 200 ㎛ was used to produce a colored glass sample that has shielding features against the low gamma-ray energy. Therefore, a weight of 70-60 wt % sand was mixed with 9-14 wt% B₂O₃, 8-10 wt% Na₂O, 4-6 wt% of CaO, 3-6 wt% Al₂O₃, in addition to 0.3% of Co₂O₃. After melting and annealing the glass sample, the X-ray diffraction spectrometry was applied to affirm the amorphous phase of the fabricated glass samples. Moreover, the X-ray dispersive energy spectrometry was used to measure the chemical composition, and the MH-300A densimeter was applied to measure the fabricated sample's density. The Makishima-Makinzie model was applied to predict the mechanical properties of the fabricated glass. Besides, the Monte Carlo simulation was used to estimate the fabricated glass sample's radiation shielding capacity in the low-energy region between 22.1 and 160.6 keV. Therefore, the simulated linear attenuation coefficient changed between 10.725 and 0.484 cm^-1, raising the gamma-ray energy between 22.1 and 160.6 keV. Also, other shielding parameters such as a half-value layer, pure lead equivalent thickness, and buildup factors were calculated.

• Journal of Radiation Protection and Research
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• 제22권3호
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• pp.219-226
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• 1997

환경시료 및 Swipe시료에서 방출되는 감마선을 측정 분석하기 위하여 극저준위 백그라운드 감마선 측정시스템을 설치하였다. 본 측정시스템은 백그라운드를 저감하기 위해 극저방사능 물질로 구성된 수동적 차폐방법, 우주선 영향을 차단하기 위한 역동시 측정법, 그리고 공기중 방사성 핵종인 라돈가스를 시스템 내부에서 제거하는 방법 등을 적용하고 있다. 적용된 백그라운드 저감법에 대한 성능시험 결과, 실험실 조건의 백그라운드 준위가 관심 대상 에너지 영역($50\;keV{\sim}2\;MeV$)에서 $10^{-2}$ order 정도로 저감되었다. 그리고 미신고 핵활동을 탐지하기 위한 관심 대상 핵종의 감마선 에너지 영역에서 평가된 시스템의 최소검출하한(MDA)값은 환경시료 분석에 적합한 것으로 평가되었다. 그러나 저에너지 영역에서는 여전히 우주선에 의한 중성자 영향이 백그라운드 요인으로 작용하고 있는 것으로 분석되었다.