• Journal of Radiation Protection and Research
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• 제22권4호
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• pp.309-317
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• 1997

비파괴적인 방법으로 방사성폐기물드럼에 대한 핵종분석을 수행할 때 드럼내 매질에 의한 방사선의 감쇠에 의해 핵종분석장치로 측정한 계수값은 실제 드럼내 방사능에 의한 계수값보다 작게 나타나 결과적으로 방사능의 측정결과가 과소평가된다. 그러므로 드럼내 매질에 의한 감쇠를 보정해 주어야 하는데 감쇠 보정방법은 드럼내 매질의 분포나 매질의 밀도에 따라 달리 적용해야 한다. 본 연구에서는 원자력발전소에서 발생하는 드럼 종류별로 모델드럼을 제작한 후 모델드럼에 표준감마선원을 넣고 핵종분석장치를 이용해 측정을 하여 드럼내 매질의 밀도를 구하였고, 이 값을 실제 매질의 밀도와 비교해 드럼종류에 따라 매질에 의한 최적의 감쇠 보정방법을 결정하였다. 그 결과 잡고체드럼의 경우에는 전송선원 보정방법과 평균밀도 보정방법, 차폐잡고체드럼의 경우 전송선원 보정방법과 두 감마선피크비교 보정방법이 최적의 감쇠 보정방법임을 알 수 있었고, 고밀도드럼인 폐수지, 농축폐액 및 폐필터드럼의 경우에는 평균밀도 보정방법과 두 감마선피크비교 보정방법을 사용해 드럼내 매질의 감쇠를 보정할 수 있다.

• 대한방사선치료학회지
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• 제17권1호
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• pp.45-55
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• 2005

목적 : 최근의 방사선치료는 정상조직의 장애는 최대한 줄이고 종양조직 선량을 높여 치료효과를 극대화 하기위하여 3차원적으로 발전되어왔으며, 이에 따른 환자 체위고정을 위한 고정기구와 보조기구의 개발이 필수적으로 요구되고 있다. 본원에서는 MR head holder, 개방형 head holder, Plan CT couch plate를 자체 제작하여 그 유용성을 평가하고 분석하였으며, 임상에 적용한 결과를 보고하고자 한다. 대상 및 방법 : MR head holder를 제작하여 진단 MR영상과 치료계획용 MR영상을 CT영상과 fusion하여 두 영상의 일치성과 정확성을 분석하였고, 개방형 head holder를 제작하여 피부선량과 선량감약 정도를 알아보았으며, 6 mm 아크릴판에 스티로폼을 부착하는 CT couch plate를 제작하여 hard plate와 artifact 정도를 비교하였다. 결과 : Head holder를 사용하지 않은 fusion영상보다 2 mm이내의 오차로 정확한 fusion을 할 수 있었고, 개방형 head holder를 사용함에 따라 피부선량을 최대 2배 이상 줄일 수 있었고, $20\%$이상 선량이 감약되는 것을 최소화할 수 있었다. Plan CT couch plate를 사용했을 때는 2단 연결, 부착 식으로 제작하여 사용이 간편하고 artifact를 현저하게 줄일 수 있었다. 결론 : MR 영상에서도 기준 좌표점을 확인할 수 있어 정확한 MR / CT fusion을 시행할 수 있었고, 향후 PET, 초음파 영상의 fusion도 연구되어야 할 것으로 사료되며, 이에 따른 고정기구의 개발도 필수적이라 할 수 있겠다. 개방형 head holder를 사용함으로써 피부선량과 선량 감약을 감소시킬 수 있었다. 이러한 치료보조기구를 자체 제작하여 고가의 외국상품을 대체할 수 있어 비용은 절감할 수 있었지만 견고성에서는 떨어지므로 가볍고 선량 감약이 적으며 강도가 강한 특수 재질의 치료보조기구가 개발되어야 할 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1483-1488
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• 2017

In order to predict and control the environmental and health impacts of ionizing radiation in environmental sources such as groundwater, it is necessary to identify the radionuclides present. Beta-emitting radionuclides are frequently identified by measuring their characteristic energy spectra. The present work shows that self-attenuation effects from volume sources result in a geometry-dependent shift in the characteristic spectra, which needs to be taken into account in order to correctly identify the radionuclides present. These effects are shown to be compounded due to the subsequent shift in the photon spectra produced by the detector, in this case an inorganic solid scintillator ($CaF_2:Eu$) monitored using a silicon photomultiplier. Using tritiated water as an environmentally relevant, and notoriously difficult to monitor case study, analytical predictions for the shift in the energy spectra as a function of depth of source have been derived. These predictions have been validated using Geant4 simulations and experimental results measured using bespoke instrumentation.

• Journal of the Optical Society of Korea
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• 제19권6호
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• pp.560-565
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• 2015

We report efficient direct coupling of THz dipole antenna pulses onto air spaced two-wire transmission lines and Teflon covered two-wire lines. The air spaced two-wire lines show TEM mode propagation with very small group velocity dispersion (GVD) and relatively low attenuation. The Teflon covered two-wire lines showed comparatively much higher attenuation and GVD. However, the Teflon covered two-wire lines show a very good guiding property when the lines are curved. Although the lines are circled only 5.0 cm in diameter, there is no additional attenuation compared to straight the lines.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.4106-4113
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• 2021

Rare earth doped barium tellurite glasses were synthesised and explored for their radiation shielding applications. All the samples showed good thermal stability with values varying between 101 ℃ and 135 ℃ based on dopants. Structural properties showed the dominance of matrix elements compared to rare earth dopants in forming the bridging and non-bridging atoms in the network. Bandgap values varied between 3.30 and 4.05 eV which was found to be monotonic with respective rare earth dopants indicating their modification effect in the network. Various radiation shielding parameters like linear attenuation coefficient, mean free path and half value layer were calculated and each showed the effect of doping. For all samples, LAC values decreased with increase in energy and is attributed to photoelectric mechanism. Thulium doped glasses showed the highest value of 1.18 cm^-1 at 0.245 MeV for 2 mol.% doping, which decreased in the order of erbium, holmium and the base barium tellurite glass, while half value layer and mean free paths showed an opposite trend with least value for 2 mol.% thulium indicating that thulium doped samples are better attenuators compared to undoped and other rare earth doped samples. Studies indicate an increased level of thulium doping in barium tellurite glasses can lead to efficient shielding materials for high energy radiation.

• Structural Engineering and Mechanics
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• 제87권5호
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• pp.499-516
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• 2023

To defend against harmful gamma radiation, new types of materials for use in the construction of heavyweight concrete (HWC) are still needed to be developed. This research introduces new materials to be employed as a partial replacement for fine aggregate (FA) to manufacture high-performance heavyweight concrete (HPHWC). These materials include hematite, black sand, ilmenite, and magnetite, with substitution ratios of 50% and 100% of FA. In this research, the hardening and fresh characteristics of HPHWC were obtained. Concrete samples' Gamma-ray linear attenuation coefficient was evaluated utilizing a gamma source of Co-60 through the thicknesses of 2.5, 5, 7.5, 10, 12.5, and 15 cm. High temperatures were studied for HPHWC samples, which were exposed to up to 700℃ for two hours. Energy-dispersive x-rays and a scanning electron microscope carried out microstructure analyses. Magnetite as an FA attained the lowest compressive strength of 87.1 MPa, but the best radiation protection characteristics and the highest density of 3100 kg/m³ were achieved. After 28 days, the attenuation efficiency of concrete mixtures was increased by 6.5% when fine sand was replaced with black sand at a ratio of 50%. HPHWC, which contains hematite, black sand, ilmenite, and magnetite, is designed to reduce environmental and health dangers and be used in medicinal, military, and civil applications.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.271-273
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• 2001

In precise measurement of air kerma with cavity ionization chambers, the effect of wall attenuation and scatter are corrected by Kwall and that of nonuniformity by Knu. Using the EGS4 code, we calculated these two correction factors. Correction factors calculated for two different-sized cylindrical ionization chamber differ by up to 0.7% from those obtained by measurements.

• Nuclear Engineering and Technology
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• 제50권6호
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• pp.944-949
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• 2018

The mass attenuation coefficients (${\mu}/{\rho}$) of food waste samples (pomegranate peel, acorn cap, lemon peel, mandarin peel, pumpkin peel, grape peel, orange peel, pineapple peel, acorn peel and grape stalk) have been measured employing a Si(Li) detector at 13.92, 17.75, 20.78, 26.34 and 59.54 keV. Also, the theoretical values of the mass attenuation coefficients have been evaluated utilizing mixture rule from WinXCOM program. The results showed that the lemon peel has the highest values of ${\mu}/{\rho}$ among the selected samples. From the obtained mass attenuation coefficients, we determined some absorption parameters such as effective atomic number ($Z_{eff}$), electron density ($N_E$) and molar extinction coefficient (${\varepsilon}$). It was found that the $Z_{eff}$ values of all food wastes lie within the range of 4.034-7.595, whereas the $N_E$ of the studied food wastes was found to be in the range of $0.301-1.720{\times}10^{25}$ (electrons/g) for present energy region.

• 한국방사선학회논문지
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• 제10권8호
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• pp.591-596
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• 2016

본 연구의 목적은 실험으로 6 MV X-선 빔의 등가에너지를 결정하는 데 있다. 6 MV X-선 빔에 대한 납의 반가층은 전리함을 사용하여 측정하였다. 선감쇠계수는 측정된 반가층을 사용하여 계산하였다. 그리고 질량감쇠계수는 납의 밀도로 선감쇠계수를 나누어 얻었다. 얻어진 질량감쇠계수의 등가에너지는 미국표준기술연구소에서 주어진 납의 광자에너지 대 질량감쇠계수 자료를 사용하여 결정하였다. 그 결과로서, 6 MV X-선 빔에 대한 등가에너지는 1.61 MeV로 결정되었다. 이 등가에너지는 Reft가 보고한 것 보다 약 30% 낮게 결정되었다. 그 원인은 납 감쇠기 사이의 공기공동의 존재에 기인한 것으로 추정된다.

• 한국분말야금학회:학술대회논문집
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• 한국분말야금학회 2002년도 제3회 최신 분말제품 응용기술 Workshop
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• pp.25-37
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• 2002

The most important industrial application of gamma radiation in characterizing green compacts is the determination of the density. Examples are given where this method is applied in manufacturing technical components in powder metallurgy. The requirements imposed by modern quality management systems and operation by the workforce in industrial production are described. The accuracy of measurement achieved with this method is demonstrated and a comparison is given with other test methods to measure the density. The advantages and limitations of gamma ray densitometry are outlined. The gamma ray densitometer measures the attenuation of gamma radiation penetrating the test parts (Fig. 1). As the capability of compacts to absorb this type of radiation depends on their density, the attenuation of gamma radiation can serve as a measure of the density. The volume of the part being tested is defined by the size of the aperture screeniing out the radiation. It is a channel with the cross section of the aperture whose length is the height of the test part. The intensity of the radiation identified by the detector is the quantity used to determine the material density. Gamma ray densitometry can equally be performed on green compacts as well as on sintered components. Neither special preparation of test parts nor skilled personnel is required to perform the measurement; neither liquids nor other harmful substances are involved. When parts are exhibiting local density variations, which is normally the case in powder compaction, sectional densities can be determined in different parts of the sample without cutting it into pieces. The test is non-destructive, i.e. the parts can still be used after the measurement and do not have to be scrapped. The measurement is controlled by a special PC based software. All results are available for further processing by in-house quality documentation and supervision of measurements. Tool setting for multi-level components can be much improved by using this test method. When a densitometer is installed on the press shop floor, it can be operated by the tool setter himself. Then he can return to the press and immediately implement the corrections. Transfer of sample parts to the lab for density testing can be eliminated and results for the correction of tool settings are more readily available. This helps to reduce the time required for tool setting and clearly improves the productivity of powder presses. The range of materials where this method can be successfully applied covers almost the entire periodic system of the elements. It reaches from the light elements such as graphite via light metals (AI, Mg, Li, Ti) and their alloys, ceramics ($AI_20_3$, SiC, Si_3N_4, $Zr0_2$, ...), magnetic materials (hard and soft ferrites, AlNiCo, Nd-Fe-B, ...), metals including iron and alloy steels, Cu, Ni and Co based alloys to refractory and heavy metals (W, Mo, ...) as well as hardmetals. The gamma radiation required for the measurement is generated by radioactive sources which are produced by nuclear technology. These nuclear materials are safely encapsulated in stainless steel capsules so that no radioactive material can escape from the protective shielding container. The gamma ray densitometer is subject to the strict regulations for the use of radioactive materials. The radiation shield is so effective that there is no elevation of the natural radiation level outside the instrument. Personal dosimetry by the operating personnel is not required. Even in case of malfunction, loss of power and incorrect operation, the escape of gamma radiation from the instrument is positively prevented.