• Proceedings of the Korean Society for Food Science of Animal Resources Conference
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• 2005.10a
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• pp.302-305
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• 2005

본 연구는 에너지 위기에 따른 고유가 시대에 에너지 소비가 많은 열처리에 의한 시유 생산을 영양적으로나 미생물학적으로 안전하게 대체할 수 있는 방법으로 감마선 조사처리에 대하여 검토하였다. 1, 2, 3, 5, 10 kGy의 감마선 조사시 당일에는 일반세균과 대장균군이 모두 검출되지 않았으나, 냉장상태에서 일주일후에는 1과 2 kGy 조사구에서 일반세균이 검출되었다. 반면 LTLT, HTST, 및 UHT 처리시에도 당일에는 일반세균이 검출되지 않았으나 일주일 후에는 LTLT 처리와 HTST 처리유에서 $10^6$ CFU/mL이상 검출된 반면 UHT 처리유에서는 일반세균이 검출되지 않아, 우유에서 미생물적으로 UHT 처리 정도의 살균효과를 거두기 위해서는 3 kGy 이상의 감마선 조사 처리가 요구되었다.

• Proceedings of the KAIS Fall Conference
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• 2002.11a
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• pp.225-228
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• 2002

현대 산업이 점차 세분화되고 산업용 반응조, 수조, 송수관 등 시설물이 증가하고 시설물의 관리가 증가함에 따라 본 논문에서는 감마선을 이용한 결합 검출기를 개발하였다. 물질의 투과성이 좋은 감마선의 특성을 이용하여 물체의 결합을 측정을 한다. 감마선이 물체를 투과하여 수집된 데이터를 영상 신호처리를 하여 이미지로 나타냄으로서 측정을 하는 사용자가 물체의 결합의 위치를 쉽게 알 수 있도록 하였으며 측정기기를 소형화하여 이동을 편리하게 하는데 본 논문은 목적을 두고 하드웨어를 제작하였으며, 물체내부의 결함은 영상 신호처리의 시뮬레이션을 통해서 확인하였다.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2017.10a
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• pp.705-707
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• 2017

Stereo-based spatial radiation detection devices can obtain not only spatial distribution information about the radiation source but also distance information from the detection device to the source. And it provides more efficient information on the source than the existing radiation imaging device. In order to provide high-speed information on the spectrum and type of gamma-ray source, a high-sensitivity detection sensor with high sensitivity is required, and a technique capable of solving the saturation phenomenon at a high dose is needed. In this paper, we constructed a high sensitivity sensor for the measurement of multiple gamma - ray spatial distributions using improved function of detection module to solve saturation to high dose and conducted research to increase the scope of a single detector. The result of this paper improves the performance of gamma ray.

• Journal of the Institute of Electronics and Information Engineers
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• v.51 no.4
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• pp.193-200
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• 2014

In this paper, the prototype of one-channel gamma-ray spectroscope for automatic radiopharmaceutical systhesis system was designed and characterized. The prototype employed CZT (CdZnTe) spear detector for gamma-ray detection and employed analog-type signal processing method. A radioactive sample Co-60 was used for measuring performance of the gamma-ray spectroscope and energy spectrum is gained with bandwidth of 1173keV. The analog board is made up of SF (shaping filter) and PHA (peak and hold amplifier) for shaping CZT output signal appropriately and ADC (analog to digital converter) and FPGA (field programmable gate array) for drawing gamma-ray spectrum by counting the digitalized gamma-ray signal data.

• Journal of the Korean Society of Radiology
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• v.14 no.7
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• pp.849-856
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• 2020

In the gamma-ray energy spectrum study, nuclide analysis through energy analysis is very important. High-purity Ge detectors, which are commonly used for gamma-ray energy measurements, are commonly used because of their high energy resolution and relatively high detection efficiency. However, in order to maintain a high energy resolution, the semiconductor detector has a problem in that it is difficult to maintain the original performance if the noise generated from the surrounding environment is not effectively blocked, and the effect of the expensive device is not achieved. Therefore, in this study, ground loop isolator (NEXT-001HDGL) was used to remove the electrical noise generated from the detector. In order to test the effect of improving energy resolution, HPGe detection device newly installed in the proton accelerator KOMAC was used. In the case of gamma-ray energy 2614 keV, the energy resolution was improved from (0.16 ± 0.02) % to (0.11 ± 0.01) %, and in the case of gamma-ray energy 662 keV of 137Cs isotope, the energy resolution was improved from (0.72 ± 0.07) % to (0.27 ± 0.03) %. This result is considered to be very useful for the gamma ray spectrum study using the HPGe detection equipment of KOMAC(Korea Multi-Purpose Accelerator Complex).

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2016.10a
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• pp.944-945
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• 2016

Gamma-ray Detector for gamma-ray imaging device is composed of a shielding body for shielding gamma-rays incident from the radiation source. Distribution of the gamma ray can be represented by the distribution information on the direction in which the detecting section and the signal through the incident hole of collimator. The role of the shield is important because all signals should be treated as noise except for the signal from the incident hole.In this paper In this paper, we have produced a compact, lightweight and Collimator shield by changing the structure and physical properties with respect to the collimator and shielding of lead-based gamma-ray detectors. And we analyzed the shielding effectiveness relative to the incident gamma ray sphere measured signal value through the gamma irradiation test facility. The results confirmed that the production and Collimator shielding the imaging device Implementing more efficient to implement.

• Journal of Sensor Science and Technology
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• v.4 no.4
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• pp.1-9
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• 1995

The ${\gamma}$-ray deposition spectra were calculated by Monte Calro method to obtain the scintillation characteristics of the ${\gamma}$-ray for BGO scintillation detector with the spherical shape of 1.25 cm radius. The code used in calculating the ${\gamma}$-ray deposition spectra was made for personal computer with qbasic language. Also the ${\gamma}$-ray energy spectra of $^{22}Na$, $^{137}Cs$ and $^{207}Bi$ were measured with the detector. The energy dependent resolution below 2000 keV for the detector was determined by estimating the standard deviation of the photopeak fitted with gaussian function, and $X^{2}$ fitting using Nardi's empirical formula. The measured spectra of $^{22}Na$ and $^{137}Cs$ were compared with the broadened spectra which were obtained by broadening the calculated ${\gamma}$-ray deposition spectra with the energy dependent resolution. The absolute efficiency and the intrinsic peak efficiency of the detector were obtained by calculating the ${\gamma}$-ray deposition spectrum with the code.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.365-372
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• 1997

이 연구의 목적은 밀도측정 및 수분함량측정용 RI 계기의 개발에 있다. 방사성동위원소를 이용하여 성토시공의 현장다짐 밀도 및 수분함량 측정에 이용되곤 있는 RI 계기는 중성자 검출부분, 감마선 검출부분, 고전압 공급부분, 마이크로 컴퓨터 부분으로 크게 나눌 수 있다. 감마선을 검출하는 G-M 검출기는 그 특징으로 인해 방사선검출 전기회로가 간단하다. 그러나 열중성자를 검출하는 He-3 검출기는 검출기에서 발생하는 신호원이 매우 작아서 검출회로의 상호 간섭으로 인한 전기적 잡음이 발생한다 이 잡음을 제거하는 것이 He-3 중성자 검출기로 열중성자를 검출하는데 중요한 문제이다. 본 연구에서 제작하는 RI 계기는 원자력법에서 제한하는 방사능 이하를 (100$\mu$Ci 의 밀봉선원) 사용하므로 종래의 RI 계기에 비해 방사선의 검출수가 줄어든다. 이에 따라 검출기의 개수를 늘려서 방사선을 검출해야 한다. 또한 본 연구에서는 He-3검출기의 검출 스펙트럼을 분석하여 적정한 방사선 검출 측정영역을 결정하였다.

• Journal of the Korean Society of Radiology
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• v.16 no.7
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• pp.953-960
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• 2022

The measurement of branching ratio of ¹⁶⁷Yb radioactive isotopes from gamma-ray spectrum of ¹⁶⁹Tm(p,3n)¹⁶⁷Yb reaction were performed by using a 100-MeV proton linear accelerator of the Korea Multi-purpose Accelerator Complex (KOMAC). The ¹⁶⁷Yb isotope has a half-life of 17.5 minutes and decays to ¹⁶⁹Tm. The gamma rays generated from the ¹⁶⁷Yb isotope were measured using an HPGe detector gamma ray spectroscopy system. The energy calibration of the detector and the efficiency measurement of the detector were determined using a standard source. The gamma rays of known main energy (62.9, 106.2, 113.3, 143.5 and 176.3 keV) were measured. On the other hand, information about the intensity of the generated gamma rays is very inaccurate. Therefore, in this study, the decay strength of the main gamma rays was accurately measured. Overall, it was different from the previously known results, and in particular, it was found that the intensity of the main decay gamma ray, such as the 113.3 and 106.2 keV gamma ray, was overestimated, and it was found that the gamma ray, such as 62.9, 116.7 and 143.5 keV was underestimated. The present results are considered to be important information in the fields of nuclear fusion, astrophysics and nuclear physics in the future.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.2
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• pp.97-104
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• 2004

Neutron induced prompt gamma-ray spectroscopy(NIPS) system measures the prompt gamma-ray emitting by the interaction of a neutron with various materials. This system will be of great benefit to scientists worldwide, since it provides the non-destructive measurement of many element in either solid or liquid wastes. In this study, the full-energy-peak (FEP) efficiency calibration for a HPGe detector was constructed in the ${\gamma}$-ray energy range from 80 keV to 8 MeV, using $^{l33}$Ba and >TEX>$^{152}Eu$ RI sources and $ ^{35}Cl(n, ${\gamma}$)^{36}Cl$ thermal neutron captured reaction. The FEP efficiency curve for the higher energies using the $^{35}Cl(n, ${\gamma}$)^{36}Cl$ reaction was normalized with the curve obtained from the RI sources, since the accurate activity of its prompt ${\gamma}$-ray is unknown. The average thermal neutron flux was theoretically calculated using the FEP efficiency curve for the KCl standard solutions. The NIPS system equipped with a ${\gamma}$-${\gamma}$ coincidence setup with two n-type coaxial HPGe detectors was considered in order to reduce the interfering ${\gamma}$-ray background. The FEP efficiency curve for the ${\gamma}$-${\gamma}$ coincidence system was also obtained for full energy range. The performance of the normal and coincidence NIPS system was tested by comparing signal-to-noise ratio in each mode using the reference sample.e.