• 센서학회지
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• 제18권2호
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• pp.173-178
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• 2009

In this study, we have fabricated a fiber-optic dosimeter using an organic scintillator and a plastic optical fiber for measuring percentage depth dose with high energy X-ray beam. The scintillating light generated in organic sensor probe embedded in a solid water are guided by 20 m plastic optical fiber to the light-measuring device such as a photodiode- amplifier system. Using a fiber-optic dosimeter and an ion chamber, percentage depth dose curves are measured with 6 and 15 MV energies of X-ray beam whose field sizes are $2\;cm\;{\times}\;2\;cm$ and $10\;cm\;{\times}\;10\;cm$.

• Applied Biological Chemistry
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• 제14권1호
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• pp.51-57
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• 1971

$CO_2$의 흡수능력(吸收能力)을 비교(比較)하기 위(爲)하여 습윤연소실험(濕潤燃燒實驗)에 있어서 Phenyl Ethylamine과 Hyamine Base를 사용(使用)하였다. 알려지고 있는 간장지질(肝藏脂質)과 균일(均一)하게 혼합(混合)된 팔미딘산-$C^{14}$을 유산(硫酸)과 인산(燐酸)으로 산화(酸化)하였다. 생성(生成)된 $CO_2$를 가느다란 비닐관(管)을 통하여 공시(供試)아민제(劑)에 포착(捕捉)시켰다. $CO_2$를 흡수(吸收)한 아민 제(劑)들을 Diotal Scintillator와 혼합(混合)하고 Liquid Scintillation Counter에 의(依)하여 그 방사능(放射能)을 측정(測定)하였다. 공시(供試)한 2종(種)아민의 계측효율(計測效率)은 $50{\sim}60%$이 었으며 방사능회수율(放射能回收率)은 거의 100%이었다. 그러나 Phenyl Ethylamine에 의(依)한 $CO_2$흡수량(吸收量)이 Hyamine Base의 그것에 비(比)하여 약(約) 2배(倍)가 되었으며 취급(取扱)하기도 용이(容易)하고 대금(代金)도 싸기 때문에 $CO_2$ 흡수제(吸收劑)로서는 Phenyl Ethylamine을 사용(使用)함이 좋을 것이다. 한편 돼지의 간장실험(肝藏實驗)에 있어서 지질(脂質)을 $CO_2$로 변화(變化)시켜 $C^{14}$의 방사능(放射能)을 측정(測定)하는 것이 지질(脂質)을 그대로 계측(計測)하는 것보다 계측효율(計測效率)이 더 증가(增加)되지 않음이 밝혀졌다.

• Nuclear Engineering and Technology
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• 제45권1호
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• pp.81-88
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• 2013

Neutron spectrum analyses of spallation neutrons are conducted in the accelerator-driven system (ADS) facility at the Kyoto University Critical Assembly (KUCA). High-energy protons (100 MeV) obtained from the fixed field alternating gradient accelerator are injected onto a tungsten target, whereby the spallation neutrons are generated. For neutronic characteristics of spallation neutrons, the reaction rates and the continuous energy distribution of spallation neutrons are measured by the foil activation method and by an organic liquid scintillator, respectively. Numerical calculations are executed by MCNPX with JENDL/HE-2007 and ENDF/B-VI libraries to evaluate the reaction rates of activation foils (bismuth and indium) set at the target and the continuous energy distribution of spallation neutrons set in front of the target. For the reaction rates by the foil activation method, the C/E values between the experiments and the calculations are found around a relative difference of 10%, except for some reactions. For continuous energy distribution by the organic liquid scintillator, the spallation neutrons are observed up to 45 MeV. From these results, the neutron spectrum information on the spallation neutrons generated at the target are attained successfully in injecting 100 MeV protons onto the tungsten target.

• 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%.

• Journal of Radiation Protection and Research
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• 제41권3호
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• pp.222-228
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• 2016

Background: We are developing a small size dosimeter for dose estimation in particle therapies. The developed dosimeter is an optical fiber based dosimeter mounting an radiation induced luminescence material, such as an OSL or a scintillator, at a tip. These materials generally suffer from the quenching effect under high LET particle irradiation. Materials and Methods: We fabricated two types of the small size dosimeters. They used an OSL material Eu:BaFBr and a BGO scintillator. Carbon ions were irradiated into the fabricated dosimeters at Heavy Ion Medical Accelerator in Chiba (HIMAC). The small size dosimeters were set behind the water equivalent acrylic phantom. Bragg peak was observed by changing the phantom thickness. An ion chamber was also placed near the small size dosimeters as a reference. Results and Discussion: Eu:BaFBr and BGO dosimeters showed a Bragg peak at the same thickness as the ion chamber. Under high LET particle irradiation, the response of the luminescence-based small size dosimeters deteriorated compared with that of the ion chamber due to the quenching effect. We confirmed the luminescence efficiency of Eu:BaFBr and BGO decrease with the LET. The reduction coefficient of luminescence efficiency was different between the BGO and the Eu:BaFBr. The LET can be determined from the luminescence ratio between Eu:BaFBr and BGO, and the dosimeter response can be corrected. Conclusion: We evaluated the LET dependence of the luminescence efficiency of the BGO and Eu:BaFBr as the quenching effect. We propose and discuss the correction of the quenching effect using the signal intensity ratio of the both materials. Although the correction precision is not sufficient, feasibility of the proposed correction method is proved through basic experiments.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2334-2338
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• 2020

In recent years, 3D printing technology has received significant research attention. Additionally, 3D printing technology is being applied to study radiation dosimeters of various materials. In this study, a plastic scintillator for 3D printing was developed in a laboratory and used to manufacture a plastic scintillation dosimeter (PSD) with a shape identical to that of the ionization chamber PTW31010. The 16-mm beam of Gamma Knife® Perfexion™ was irradiated to derive the absorbed dose rates of the PSD and PTW31010; they were subsequently compared with the dose rates of the treatment plan. The differences in the dose rates of the Gamma Knife treatment plan and the absorbed dose rates of PTW31010 were within 0.87%. The difference between the dose rates of the Gamma Knife treatment plan and the absorbed dose rates of the PSD were within 4.1%. A linear fit of the absorbed dose rates of four shots involving different dose rates and irradiation angles yielded an adjusted R-square value exceeding 0.9999. A total of 10 repeated measurements were conducted for the same shot to confirm its reproducibility, with a relative error of 0.56%.

• 대한방사선기술학회지:방사선기술과학
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• 제28권1호
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• pp.9-12
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• 2005

본 연구에서는 엑스선 또는 감마선 원거리 측정용 초소형 방사선 센서를 개발하기 위해서 발광 스펙트럼이 다른 여러 종류의 무기 섬광체를 이용하여 필름형태의 센서부를 제작하였고, 방사선으로부터 발생되는 섬광량을 광검출기 및 광파워미터로 측정하였다. 본 연구 결과, 개발 가능한 방사선 센서는 직경 1 mm의 플라스틱 광섬유를 사용하여 전자기파 장애로부터 간섭을 받지 않음과 동시에 원거리 측정 및 신속, 정확한 방사선 계측이 가능하고 초소형, 초경량의 특성을 지니기 때문에 방사선 치료 시 고 분해능의 방사선 계측이 가능할 것으로 기대된다.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.1036-1042
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• 2020

Fast-Neutron Multiplicity Counter based on Liquid Scintillator Detector can directly measure the fast neutron multiplicity emitted by UO₂ rod. HPGe gamma spectrometer; which has superior energy resolution; is routinely used for the gamma energy spectrum measurement. Combing Fast-Neutron Multiplicity Counter and HPGe γ-spectrometer, the n/γ joint measurement system is developed. The fast neutron multiplicity and gamma energy spectrum of UO₂ rod assemblies under different conditions are measured by the n/γ joint measurement system. The induced fission rate and the ²³⁵U abundance, thereby the ²³⁵U mass; can be obtained for UO₂ rod assemblies. The ²³⁵U mass deviation of the measured value from the reference value is less than 5%. The results show that the n/γ joint measurement system is effective and applicable in the measurement of the ²³⁵U mass in samples.

• Journal of the Optical Society of Korea
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• 제18권3호
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• pp.256-260
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• 2014

Columnar-structured cesium iodide (CsI) scintillators doped with thallium (Tl) are frequently used as x-ray converters in medical and industrial imaging. In this study we investigated the imaging characteristics of CsI:Tl films with various reflective layers-aluminum (Al), chromium (Cr), and titanium dioxide ($TiO_2$) powder-coated on glass substrates. We used two effusion-cell sources in a thermal evaporator system to fabricate CsI:Tl films on substrates. The scintillators were observed via scanning electron microscopy (SEM), and scintillation characteristics were evaluated on the basis of the emission spectrum, light output, light response to x-ray dose, modulation transfer function (MTF), and x-ray images. Compared to control films without a reflective layer, CsI:Tl films with reflective layers showed better sensitivity and light collection efficiency, and the film with a $TiO_2$ reflective layer showed the best properties.

• 한국방사선학회논문지
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• 제17권1호
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• pp.17-23
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• 2023

본 연구에서는 중성자 반응단면적이 높은 Li, Gd 및 B을 모체로 구성된 중성자 검출용 Li₆Y_0.5Gd_0.5(BO₃)₃ (LY_0.5G_0.5BO) 섬광체의 전자포획준위에 대하여 조사하였다. LY_0.5G_0.5BO 섬광 단결정에 대하여 열형광곡선을 측정하고 이를 피크형상법, 초기상승법 및 기계학습 알고리즘을 이용하여 분석하여 전자포획준위의 물리적인 인자를 평가하였다. LYGBO 섬광 단결정의 열형광곡선은 단일 피크로 이루어져 있으며, 이 피크를 분석한 결과 전자포획준위의 활성화에너지, 발광차수 및 주파수인자는 각각 0.61 eV, 1.1 및 1.7×10⁷ s^-1이었다. 아울러 기계학습을 이용한 섬광체의 열형광 해석의 가능성을 확인하였다.