• Journal of the Korean Society of Radiology
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• v.15 no.6
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• pp.869-875
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• 2021

The purpose of this study is to derive a formula for calculating the effective energy of an X-ray beam generated by a CT simulator. Under 90, 120, and 140 kVp X-ray beams, the CT number calibration insert part of the AAPM CT performance phantom was scanned 5 times with a CT simulator. The CT numbers of polyethylene, polystyrene, water, nylon, polycarbonate, and acrylic were measured for each CT slice image. The average value of CT number measured under a single tube voltage and the linear attenuation coefficients corresponding to each photon energy calculated from the data of the National Institute of Standards and Technology were linearly fitted. Among the obtained correlation coefficients, the photon energy having the maximum value was determined as the effective energy. In this way, the effective energy of the X-ray beam generated at each tube voltage was determined. By linearly fitting the determined effective energies(y) and tube voltages(x), y=0.33026x+30.80263 as an effective energy calculation formula was induced.

• Journal of the Korean Society of Radiology
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• v.9 no.6
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• pp.375-379
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• 2015

The purpose of this study is to determine the effective energy of a polyenegetic X-ray beam. The half value layer(HVL) of aluminum for 80 kVp X-ray beam was measured by using optically stimulated luminescent nanoDot dosimeters(OSLnDs). The linear attenuation coefficient(${\mu}$) was calculated using the measured HVL. And the mass attenuation coefficient(${\mu}/{\rho}$) was obtained by dividing the linear attenuation coefficient by the density(${\rho}$) of aluminum. The effective energy($E_{eff}$) of the obtained mass attenuation coefficient was determined using data of the X-ray mass attenuation coefficients for photon energies of aluminum given by National Institute of Standards and Technology(NIST). As a result, the HVL value is 2.262 mmAl. The ${\mu}$ value is $3.06cm^{-1}$. The ${\mu}/{\rho}$ value is $1.114cm^2/g$. And the $E_{eff}$ value was determined at 29.79 keV.

• Journal of the Korean Society of Radiology
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• v.13 no.4
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• pp.517-522
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• 2019

The purpose of this study is to determine the effective energy of CT X-ray beams by using the CT slice images of a CT number calibration insert part in the AAPM CT performance phantom. The CT number calibration insert part in the AAPM CT performance phantom was scanned five times by using a CT canner for 80, 100 and 120 kVp X-ray beams. The average value of CT numbers of each pin were measured for each CT slice image. The correlation coefficients were obtained by linear fit between the average value of CT numbers measured and liner attenuation coefficient under different energy at each pin calculated from data of NIST. A photon energy corresponding to the maximum value of the obtained correlation coefficient was determined as an effective energy. As a result, the effective energy was 56, 62 and 66~67 keV, respectively, for 80, 100 and 120 kVp X-ray beams.

• Journal of the Korean Society of Radiology
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• v.17 no.6
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• pp.809-817
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• 2023

Single source and dual source measurements using anthropomorphic phantoms in which the phantoms are lined up in human body equivalents use OSLD (Optically Stimulated Luminescence Dosimeter), so the effective dose is calculated using OSLD. For hospital images, SNR (Signal to Noise Ratio) and CNR (Contrast to Noise Ratio) were measured in MCA (Middle Cerebral Artery) for single source and dual source, and for phantom images, SNR and CNR were measured for brain parenchyma of single source and dual source. For hospital imaging, SNR and CNR were measured in MCA for both single-source and dual-source, and for phantom images, SNR and CNR were measured for brain parenchyma from single-source and dual-source. As a result of comparing the SNR and CNR of the hospital image and the phantom image, there was no statistical difference. Comparing patient doses in hospital images, the effective dose of the dual source was 53.53% less and the effective dose of the dual energy phantom was 57.94% less. The dose can be increased in other areas, but the cerebrovascular area is useful because the dose is small.

• KOREAN POULTRY JOURNAL
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• v.5 no.1 s.39
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• pp.95-99
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• 1973

사료중에 포함된 총에너지는 이것이 전량 동물에게 이용되는 것이 아니고 여러가지 형태로서 손실이 일어나는 것이다. 분과 뇨 그리고 열량증가로서의 에너지의 손실을 공제하고 실제로 동물에게 이용되는 에너지를 정미 에너지라고 하며 정미에너지는 다시 생산과 유지에 쓰이기 위한 것이다. 동물에게 실제로 이용되는 유효에너지인 정미에너지가를 추정하는데는 가소화에너지, 대사에너지, 생산에너지가 흔히 사용되고 있으나 그중에서 구하기가 비교적 쉽고 유효에너지의 훌륭한 척도가 될 수 있는 대사에너지(ME)의 개념이 가장 많이 쓰이고 있다. 대사에너지의 약점은 동물의 체내에서 일어나는 에너지의 손실중 열량증가(Specific dynamic action)로서의 손실을 고려하지 않았다는데 있으며 이로 인해서 몇가지 문제점들이 발견되고 있으나 지금까지 많은 연구가 이루어져 왔으며 앞으로도 계속해서 검토되어야 할 것이다. 성장중의 병아리를 대상으로 ME를 추정하는 방법은 많은 학자들에 의해서 창안되었으며 실제로 많은 단미사료의 ME함량에 대한 데이타는 손쉽게 구할 수 있다. 그러나 산란계를 대상으로 한 시험은 많지 않았으며 병아리로부터 얻어진 데이타를 산란계에 적용하고 있는 실정인바, 어떤 사료에 대해서는 병아리와 산란계 사이에 이용성이 다를 수 있다는 점에서 앞으로는 보다 많은 단미사료에 대해서 산란계로부터 직접 측정하여 이용함이 바람직하다. 생물학적인 사양시험을 통해서 직접 측정된 ME가와 그 사료의 화학적 성분함량과의 관계를 조사함으로써 화학적 조성으로 ME가를 추정하는 방법의 개발은 그 추정치가 반드시 정확하지는 않다 하더라도 사전 지식이 없는 새로운 단미 사료에 부딛쳤을때 그 사료의 대략적인 에너지가를 짐작하는데 도움을 준다. 각종 단미사료의 ME함량에 대해서 우리나라에서 측정된 자료가 많지 않고 대부분 외국의 데이타를 이용하고 있는 실정인바 앞으로는 우리나라에서 실제 사용되고 있는 많은 단미사료에 대한 ME가 직접 국내에서 측정, 이용되어야 할 것으로 생각한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.1047-1053
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• 1995

한국의 장기 에너지공급 전략에서 에너지수요 및 환경제약에 따른 원자력에너지의 역할을 평가하기 위해 에너지수급 최적화모형인 MESSAGE를 이용하였다. 에너지수급 네트워크의 입력자료로 필요한 유효에너지 수요를 예측하기 위해 새로운 프로그램을 개발하였고, 이 결과를 이용하여 1993년부터 2040년까지 원자력계통을 포함한 전체 에너지계통에 대한 최적화를 수행하였으며, 노형전략 및 핵연료주기전략, 원자력에너지의 확대이용 방안 등을 제시하였다. 한국에서 원자력 확대이용에 대한 핵심 요인은 경제성장 규모, 화석연료의 이용가능성, 이산화탄소 배출규제, 부지 및 대중수용성에 의해 제한 받는 원자력 자체의 공급능력이 될 것이다.

• Electric Engineers Magazine
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• v.218 no.10
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• pp.25-32
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• 2000

유효전력, 리액티브 전력 및 피상전력은 역률 보정을 나타내기 위하여 보통 사용하는 전력 삼각형의 세가지 요소들이다. 킬로와트로 측정되는 유효전력은 유효한 일로 직접적으로 변환되는 전력이며 Volt-Amepere Reactance 또는 Kilo Volt Amp Reactance로 측정되는 무효전력은 모터와 같은 유도성 부하의 구동을 위해 필요한 전기자기장을 발생하기 위한 전기 에너지이다.

• Journal of the Korean Society of Radiology
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• v.17 no.4
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• pp.507-514
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• 2023

The purpose of this study is to find a formula that can easily calculate the effective photon energy in the X-ray beam of mammography. The tube voltage measured for each set tube voltage was obtained using the X2 MAM Sensor. The mass attenuation coefficient for aluminum of the aluminum filter was obtained from the half value layer measurement from each measured tube voltage X-ray beam. The mass attenuation coefficient of aluminum obtained from each measured tube voltage X-ray beam was corresponded to the mass attenuation coefficient of aluminum for each photon energy obtained from NIST. The photon energy corresponding to the matching mass attenuation coefficient was determined as the effective photon energy. The formula for calculating the determined effective photon energy was obtained by polynomial matching of the effective photon energy for each tube voltage in the Origin pro 2019b statistical program as y = 28.98968-1.91738x + 0.07786x2-0.000946717x3. Here, x is the measuring tube voltage and y is the effective photon energy. The calculation formula of the effective photon energy of the mammography X-ray beam obtained in this study is considered to be very useful in obtaining the interaction coefficient between the X-ray beam and a certain substance in clinical practice.

• Journal of the Korean Society of Radiology
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• v.16 no.1
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• pp.61-66
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• 2022

The purpose of this study is to derive photon energy fluence and mass energy absorption coefficient for 1 Gy of absorbed dose of water in brachytherapy using an Ir¹⁹² source. From the radiotherapy physics written by Khan, the half-value of lead for the gamma ray beam of the Ir¹⁹² source was obtained. The linear attenuation coefficient and the mass attenuation coefficient were calculated from the obtained half-value layer of lead. By matching the calculated lead mass attenuation coefficient with the NIST mass attenuation coefficient data, the photon energy of the matching mass attenuation coefficient was determined as the effective energy. By matching the determined effective energy with the photon energy of the NIST data on the mass energy absorption coefficient of water, the mass energy absorption coefficient of water was obtained as 0.03273 cm²/g(32.73 cm²/kg). The photon energy fluence was calculated as 0.03055 J/cm² by dividing the obtained mass energy absorption coefficient (32.73 cm²/kg) by the absorbed dose of water 1 Gy.

• Journal of Radiation Protection and Research
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• v.24 no.4
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• pp.205-213
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• 1999

Effective dose conversion coefficients from unit activity radionuclides contaminated on the ground surface were calculated by using MCNP4A rode and male/female anthropomorphic phantoms. The simulation calculations were made for 19 energy points in the range of 40 keV to 10 MeV. The effective doses E resulting from unit source intensity for different energy were compared to the effective dose equivalent $H_E$ of previous studies. Our E values are lower by 30% at low energy than the $H_E$ values given in the Federal Guidance Report of USEPA. The effective dose response functions derived by polynomial fitting of the energy-effective dose relationship are as follows: $f({\varepsilon})[fSv\;m^2]=\;0.0634\;+\;0.727{\varepsilon}-0.0520{\varepsilon}^2+0.00247{\varepsilon}^3,\;where\;{\varepsilon}$ is the gamma energy in MeV. Using the response function and the radionuclide decay data given in ICRP 38, the effective dose conversion coefficients for unit activity contamination on the ground surface were calculated with addition of the skin dose contribution of beta particles determined by use of the DOSEFACTOR code. The conversion coefficients for 90 important radionuclides were evaluated and tabulated. Comparison with the existing data showed that a significant underestimates could be resulted when the old conversion coefficients were used, especially for the nuclides emitting low energy photons or high energy beta particles.