• Journal of Radiation Protection and Research
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• 제12권2호
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• pp.19-27
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• 1987

황산망간 용액조장치의 $^{56}Mn\;{\gamma}$선 검출효율을 결정하는데 $^{56}Mn$용액의 방사능을 절대측정하는 것은 필수적이다 $^{56}Mn$시료를 제작하기 위하여 99.99%의 순도를 갖는 Mn금속조각 13.718mg되는 시료를 한국에너지연구소 TRIGA MARK-II 원자로의 중성자선속이 약 $10^{13}n/cm^2{\cdot}s$되는 열중성자장에서 12분간 조사시켰다. 중성자 방사화된 $^{56}Mn$금속시료를 0.1N-HCI 용액 50ml 용해시켜서 $^{56}Mn$시료를 제작하여 $4{\pi}{\beta}-{\gamma}$ 동시계수기술로 방사능을 측정한 결과 불확도 0.366%를 갖는 값으로서 1987년 10월 15일 0 시를 기준하여 408.070kBq/mg을 얻었다.

• Journal of Radiation Protection and Research
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• 제33권4호
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• pp.173-181
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• 2008

실내 라돈 검출기의 신뢰성 평가를 위해서 미국 Landauer사의 $RadTrak^{(R)}$, 헝가리 Radosys사의 $Radopot^{(R)}$, 그리고 미국 Rad elec 사의 $E-PERM^{(R)}$ 검출기의 성능을 비교 검토하였다. RadTrak과 Radopot에 대한 라돈 표준 챔버 테스트 결과, $AlphaGUARD^{(R)}$ 검출 결과와 비교하여 각각 -13.2%. -6.0%로 라돈 검출기 성능평가기준인 ${\pm}20%$ 이내에 포함되는 결과를 보였다. 또한, 실제 현장에서의 장기간 측정을 통한 성능을 평가하기 위하여 약 100여개의 가옥 내 동일한 장소에 각각의 검출기를 1 년 동안 설치하여 비교하였다. RadTrak 과 Radopot 의 비교에서는 매우 좋은 상관관계 ($R^2$ = 0.91)를 보였지만, E-PERM과 Radopot의 비교결과, 거의 상관성을 파악 할 수 없었다($R^2$ = 0.021). 또한, E-PERM을 이용한 연평균 전국 실내 공간감마선량률 등준위도는 Portable Ion Chamber를 이용한 전국 실외 공간감마선량률 등준위도와 다소 상이한 결과를 보였다. 실험 결과를 바탕으로 향 후 대규모 라돈농도조사에 필요한 검출기 선정 요건에 대해서 논의 하였다.

• 한국축산식품학회지
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• 제30권1호
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• pp.124-132
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• 2010

육가공 산업에서 원료로 이용되고 있는 향신료의 위생화를 위하여 대표적인 살균 기술인 감마선과 전자선의 조사효과를 비교하였다. 미생물 오염도를 측정한 결과 대부분의 시료에서 1.5 to 3.8 Log CFU/g의 일반호기성 미생물이 나타났으나, 강황 및 로즈마리에서는 미생물이 검출되지 않았다. 검출된 시료에서는 조사에 의해 효과적인 것으로 미생물이 감소하였으며, 감마선이 전자선보다 효과적으로 미생물을 사멸하였다. 검출된 미생물을 동정한 결과 Bacillus spp. 및 Staphylococcus spp.으로 확인하였다. B. cereus 및 S. aureus에 대한 방사선 감수성 측정 결과 0.19-0.63 kGy로 확인되었으며, 전자선 보다 감마선에 대한 내성이 약한 것으로 확인되었다. Ames test를 이용하여 방사선 조사에 의한 향신료의 유전독성학적 안전성을 평가한 결과, 조사에 의한 돌연변이원성은 관찰되지 않았다. 이상의 결과를 종합하여 볼 때, 향신료의 위생화를 위한 살균방법으로 방사선 조사기술이 효과적으로 판단되며, 감마선(>4 kGy, <6 kGy)이 전자선보다 효과적으로 미생물을 제어하는 것으로 나타났다.

• 동위원소회보
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• 제21권4호
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• pp.55-65
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• 2006

A passive type radon monitor adopting two silicon PIN detector as radiation detector has been developed, manufactured and test-evaluated. A radiation signal processing circuit has been electronically tested and then the radiation detection characteristics of this instrument has been performance-tested by using reference radon concentration and a reference photon radiation field. As a result, in a electronic performance test, radiation signals from each detector were well observed in each signal processing circuit. The radiation detection sensitivity of this instrument after several test-irradiations to a Cs-137 gamma radiation source and a standard radon concentration appeared to be 1.37 cph/$\mu$Svh-1 and 1.66 pCi/L respectively. The developed radon monitor in this paper could be used conveniently in monitoring of radon concentration in buildings which population utilize in Korea.

• Journal of Radiation Protection and Research
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• 제43권4호
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• pp.154-159
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• 2018

Background: To prevent small leakage accidents, a real-time and direct detection system for small leaks with a detection limit below that of existing systems, e.g. $0.5gpm{\cdot}hr^{-1}$, is required. In this study, a small-size beta detector, which can be installed inside the reactor containment (CT) building and detect small leaks directly, was suggested and its feasibility was evaluated using MCNPX simulation. Materials and Methods: A target nuclide was selected through analysis of radiation from radionuclides in the reactor coolant system (RCS) and the spectrum was obtained via a silicon detector simulated in MCNPX. A window was designed to reduce the background signal caused by other nuclides. The sensitivity of the detector was also estimated, and its shielding designed for installation inside the reactor CT. Results and Discussion: The beta and gamma spectrum of the silicon detector showed a negligible gamma signal but it also contained an undesired peak at 0.22 MeV due to other nuclides, not the $^{16}N$ target nuclide. Window to remove the peak was derived as 0.4 mm for beryllium. The sensitivity of silicon beta detector with a beryllium window of 1.7 mm thickness was derived as $5.172{\times}10^{-6}{\mu}Ci{\cdot}cc^{-1}$. In addition, the specification of the shielding was evaluated through simulations, and the results showed that the integrity of the silicon detector can be maintained with lead shielding of 3 cm (<15 kg). This is a very small amount compared to the specifications of the lead shielding (600 kg) required for installation of $^{16}N$ gamma detector in inside reactor CT, it was determined that beta detector would have a distinct advantage in terms of miniaturization. Conclusion: The feasibility of the beta detector was evaluated for installation inside the reactor CT to detect small leaks below $0.5gpm{\cdot}hr^{-1}$. In future, the design will be optimized on specific data.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2014년도 춘계학술대회
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• pp.373-376
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• 2014

전 세계적으로 해운물류 안전 보안체계가 강화됨에 따라 국가물류보안 체계 구축을 위한 해운물류 안전 보안 핵심기술 개발이 이루어지고 있다. 이러한 국제적 정서에 발맞추어, 국내에서도 감마선 핵종을 검출할 수 있는 휴대용 방사선 검출 장치에 대한 관심이 높아지고 있다. 본 논문에서는 Cortex-A9을 이용한 휴대용 방사선 검출장치 플랫폼 검출 성능의 향상을 위한 연구를 제안한다.

• 방사선산업학회지
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• 제8권1호
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• pp.11-15
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• 2014

In this study, we investigated the applicability of the photostimulated luminescence (PSL), thermoluminescence (TL) and electron spin resonance (ESR) methods for freeze dried fruits which are not allowed to be irradiated in Korea. Apples and persimmons samples that had been dried with a freeze drier were irradiated at a dose of 1, 3, 5, 7, and 10 kGy, using a gamma radiator with a cobalt-60 source. With the PSL method, the dried apples showed photon counts of less then 700 counts/60 s (negative) in all the samples, whereas the dried persimmons that were gamma-irradiated above 3 kGy yielded photon counts of between 700 and 5,000 counts/60 s (intermediate). The TL results showed that this technique is useful for detecting irradiated samples; the TL ratios ($TL_1/TL_2$) measured for the food samples at an irradiation dose of 1 kGy were 0.13 for dried apples and 0.79 for dried persimmons. With regard to the results of ESR spectroscopy, the strength of the ESR signals from the dried fruits increased linearly in a dosedependent manner. However, the characteristic signal was not found in all the samples. In conclusion, the TL methods only can be used for the detection of gamma-irradiated dried apples and persimmons.

• 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.

• Nuclear Engineering and Technology
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• 제52권1호
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• pp.155-163
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• 2020

To investigate the optimal detector material for prompt gamma imaging during boron neutron capture therapy, in this study, we evaluated the characteristic regarding radiation reaction of available detector materials using a Monte Carlo simulation. Sixteen detector materials used for radiation detection were investigated to assess their advantages and drawbacks. The estimations used previous experimental data to build the simulation codes. The energy resolution and detection efficiency of each material was investigated, and prompt gamma images during BNCT simulation were acquired using only the detectors that showed good performance in our preliminary data. From the simulation, we could evaluate the majority of detector materials in BNCT and also could acquire a prompt gamma image using the six high ranked-detector materials and lutetium yttrium oxyorthosilicate. We provide a strategy to select an optimal detector material for the prompt gamma imaging during BNCT with three conclusions.

• 동아시아식생활학회지
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• 제17권6호
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• pp.816-821
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• 2007

The physical properties and sensory characteristics of acorn starch gels (Dotori Mook), which were gamma-irradiated up to 3 kGy, were evaluated during storage at $4^{\circ}C$. Even at the dose of 2 kGy, the gamma irradiation decreased total bacteria in the Dotori Mook during 5 days of storage, to lower than the detection limit $(10^2CFU/g)$. The hardness of the control sample increased according to the days of storage, while the gamma irradiated samples had decreased hardness according to the irradiation dose. The sample irradiated at 3 kGy maintained the same hardness as the control at day 0 of storage. Irradiation did not affect the Hunter color values. No significant differences were observed in off-odor, color, springiness, and overall acceptability (p<0.05) at the irradiation dose of 2 kGy. It can be concluded that the irradiation of Dotori Mook, up to 2 kGy, does not affect the quality of the Mook during storage, with regard to texture and sensory characteristics. Moreover, the irradiated Mook was superior in maintaining hardness and had prolonged shelf-life time by sanitation.