• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2572-2580
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• 2020

Emerging gamma ray detection applications that utilize neutron-based interrogation result in the prompt emission of high-energy (>2 MeV) gamma-rays. Rapid imaging is enabled by scintillators that possess high density, high atomic number, and excellent energy resolution. In this paper, we evaluate the bright (50,000 photons/MeV) oxide scintillator, cerium-doped Gd₂Al₂Ga₃O₁₂ (GAGG(Ce)). A silicon photomultiplier (SiPM) array is coupled to a GAGG(Ce) scintillator array (12 × 12 pixels) and integrated into a coded-aperture based gamma-ray imaging system. A resistor-based symmetric charge division circuit was used reduce the multiplicity of the analog outputs from 144 to 4. The developed system exhibits 9.1%, 8.3%, and 8.0% FWHM energy resolutions at 511 keV, 662 keV, and 1173.2 keV, respectively. In addition, a pixel-identification resolution of 602 ㎛ FWHM was obtained from the GAGG(Ce) scintillator array.

• 천문학회보
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• 제39권1호
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• pp.80-80
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• 2014

Dynamics of a globular cluster (GC) is dominated by behaviors of high-mass components such as neutron stars or black holes (BHs). Massive components in a cluster are segregated into the cluster core and some of them are ejected by dynamical interactions. In this study, we perform N-body simulations of GCs adapting two BH mass components, $10M_{\odot}$ and $20M_{\odot}$. Previous studies which mostly assume single-mass BHs suggested a rapid collapsing and escaping of BHs. A cluster with a two-component BH mass spectrum, however, retains a large fraction of $10M_{\odot}$ BHs longer. In addition to their roles in cluster dynamics, massive components in binaries are one of important sources of gravitational waves (GWs). We investigate properties of BH binaries escaped from the cluster and discuss their implications for GW detection.

• 천문학회보
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• 제44권2호
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• pp.35.3-35.3
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• 2019

The new era of multi-messenger astronomy (MMA) has arrived in 2017 with the detection of the binary neutron star merger in both gravitational wave (GW) and electromagnetic radiation (EM). Now, the new run of GW detectors are providing numerous GW events and the number GW events are expected to increase dramatically in future as the GW sensitivities improve. When the GW studies are combined with EM counterpart observations, a great synergy is expected in many areas of study such as the physical process following the compact object merger, the environment of such events (and galaxy evolution), and cosmology, Therefore, it has now become crucial to identify and characterize these GW events in optical/IR EM. In the past, we have been performing optical/NIR observation of GW events using a worldwide network of more than 10 telescopes, and are getting more actively involved in MMA of GW sources. In this talk, we will present our network of telescopes, the EM follow-up observation results of GW events including GW170817 and the O3 events in 2019, and the current issues in MMA. We will also give the future prospects of MMA, showing the forecast for the GW events and the outlook of EM MMA observations.

• 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.

• 대한화학회지
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• 제15권4호
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• pp.191-197
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• 1971

고 순도 팔라듐 금속(99.9%)에 함유된 루테늄 함량을 $^{104}Ru(n,{\gamma};{\beta}^-)^{105}Rh$의 핵반응에 의하여 생성된 $^{105}Rh$의 방사능을 계축하므로써 결정하였다. 원자로에서 조사된 팔라듐 시료와 루테늄 표준시료를 왕수 처리 및 과산화나트륨으로 용융시킨다음 $^{105}Rh$을 음이온 및 양이온 교환수지로 분리하였다. 팔라듐 시료로 부터 얻은 $^{105}Rh$의 방사능을 루테늄 표준시료로 부터 얻은 $^{105}Rh$의 방사능과 비교하므로서 루테늄의 함량을 결정하였다. 본 방법으로 구한 루테늄의 검출한계는 팔라듐 10mg을 시료로 하였을 때 약 1ppm이었으며 이 검출 감도는 $^{102}Ru(n,{\gamma})^{103}Ru$의 핵반응을 사용한 종래의 방사화 분석에 비해 약 40배 더 예민하였다.

• 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.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3732-3753
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• 2023

The Real-time Analysis for Particle-transport and In-situ Detection (RAPID) Code System, developed based on the Multi-stage Response-function Transport (MRT) methodology, enables real-time simulation of nuclear systems such as reactor cores, spent nuclear fuel pools and casks, and sub-critical facilities. This paper presents the application of a novel fission matrix-based burnup methodology to the well-characterized JSI TRIGA Mark II research reactor. This methodology allows for calculation of nuclear fuel depletion by combination and interpolation of RAPID's burnup dependent fission matrix (FM) coefficients to take into account core changes due to burnup. The methodology is compared to experimentally validated Serpent-2 Monte Carlo depletion calculations. The results show that the burnup methodology for RAPID (bRAPID) implemented into RAPID is capable of accurately calculating the k_eff burnup changes of the reactor core as the average discrepancies throughout the whole burnup interval are 37 pcm. Furthermore, capability of accurately describing 3D fission source distribution changes with burnup is demonstrated by having less than 1% relative discrepancies compared to Serpent-2. Good agreement is observed for axially and pin-wise dependent fuel burnup and nuclear fuel nuclide composition as a function of burnup. It is demonstrated that bRAPID accurately describes burnup in areas with high gradients of neutron flux (e.g. vicinity of control rods). Observed discrepancies for some isotopes are explained by analyzing the neutron spectrum. This paper presents a powerful depletion calculation tool that is capable of characterization of spent nuclear fuel on the fly while the reactor is in operation.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.328-332
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• 2016

Background: Boron Neutron Capture Therapy (BNCT) is a new radiation therapy. In BNCT, there exists some very critical problems that should be solved. One of the severest problems is that the treatment effect cannot be known during BNCT in real time. We are now developing a SPECT (single photon emission computed tomography) system (BNCT-SPECT), with a cadmium telluride (CdTe) semiconductor detector. BNCT-SPECT can obtain the BNCT treatment effect by measuring 478 keV gamma-rays emitted from the excited state of $^7Li$ nucleus created by $^{10}B(n,{\alpha})$ $^7Li$ reaction. In the previous studies, we investigated the feasibility of the BNCT-SPECT system. As a result, the S/N ratio did not meet the criterion of S/N > 1 because deterioration of the S/N ratio occurred caused by the influence of Compton scattering especially due to capture gamma-rays of hydrogen. Materials and Methods: We thus produced an arrayed detector with two CdTe crystals to test cross talk phenomenon and to examine an anti-coincidence detection possibility. For more precise analysis for the anti-coincidence detection, we designed and made a collimator having a similar performance to the real BNCT-SPECT. Results and Discussion: We carried out experiments with the collimator to examine the effect of cross talk of scattering gamma-rays between CdTe elements more practically. As a result of measurement the coincidence events were successfully extracted. Conclusion: We are now planning to carry out evaluation of coincidence rate from the measurement and comparison of it with the numerical calculations.

• 한국의학물리학회지:의학물리
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• 제23권3호
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• pp.162-168
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• 2012

양성자 치료에서 치료의 목표를 달성하고 환자의 안전을 제고하기 위해 인체 내 양성자 빔의 분포를 확인하는 것이 중요하다. 양성자 선량분포와 밀접한 관계가 있는 즉발감마선의 2차원 분포 측정을 위하여 본 연구팀에서는 다수의 CsI(Tl) 섬광체가 1차원 종형으로 배열된 검출기 배열과 집속장치 및 다채널 신호처리 장치로 이루어진 측정장치를 개발하고 있다. 이에 본 연구에서 몬테칼로 기반의 MCNPX 코드를 이용하여 최적화된 측정 장치를 설계하고자 하였다. 즉발감마선을 효과적으로 측정하기 위해 CsI(Tl) 섬광체의 크기를 $6{\times}6{\times}50mm^3$로 결정하였으며, 배경감마선의 영향을 최소화하고 빔의 진행방향에서 수직방향으로 발생하는 즉발감마선만 측정하기 위해 집속장치의 구멍 크기는 면적 $6{\times}6mm^2$, 길이 150 mm로 최적화되었다. 150 MeV 양성자 빔에 대한 성능 예측 전산모사연구를 수행한 결과, 본 연구에서 최적화된 측정 장치를 통해 즉발감마선 2차원 분포를 측정할 수 있었으며, 1 mm 오차범위에서 양성자 빔의 비정을 결정할 수 있었다. 이를 바탕으로 현재 다채널의 신호처리 장치를 개발하고 있으며 실제 양성자 빔을 이용한 즉발감마선 분포측정을 통해 측정 장치의 성능을 검증할 것이다.

• 분석과학
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• 제18권1호
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• pp.51-58
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• 2005

A comparison of the analytical data obtained by three $k_0$-NAA software programs was carried out using both the airborne particulate matter collected from an urban site and the certified reference materials of the air filter and urban dust to evaluate the performance of the analysis. The individual $k_0$-NAA standardization methods of three countries, Korea, China and Vietnam which had been modified from the well established $k_0$-program were used for the comparative analysis. The measured concentrations of 30 elements from the two kinds of air samples based on this software were in agreement with each other within about 20% analytical error except for a few elements. By contrast, the results of China and Vietnam were moderately higher than that of Korea due to a systematic error associated with the detection efficiency, gamma peak analysis and geometric effect.