• Nuclear Engineering and Technology
• /
• 제53권11호
• /
• pp.3764-3771
• /
• 2021

Based on the convolutional neural network (CNN), a novel technique is investigated for lost gamma source detection in a room. The CNN is trained with the result of a GEANT4 simulation containing a gamma source inside a meshed room. The dataset for the training process is the deposited energy in the meshes of different n-step paths. The neural network is optimized with parameters such as the number of input data and path length. Based on the proposed method, the place of the gamma source can be recognized with reasonable accuracy without human intervention. The results show that only by 5 measurements of the energy deposited in a 5-step path, (5 sequential points 50 cm apart within 1600 meshes), the gamma source location can be estimated with 94% accuracy. Also, the method is tested for the room geometry containing the interior walls. The results show 90% accuracy with the energy deposition measurement in the meshes of a 5-step path.

• Nuclear Engineering and Technology
• /
• 제55권1호
• /
• pp.229-237
• /
• 2023

The mechanics underlying photon and electron interactions was validated using our developed Brachytherapy computer code for high Dose Rate (HDR). By comparing the photon cross-section utilizing multiple physics libraries in the developed code, the results were benchmarked against experimental and theoretical findings. Klein-Nishina and experimental cross-section results were in good agreement with the Livermore library results. For two therapeutically relevant materials, the first scattered electron range was measured within 1 mm and 2 mm, which has significant implications for the interpretation of the kernel dose spikes observed in previous research.

• 한국의학물리학회지:의학물리
• /
• 제27권3호
• /
• pp.125-130
• /
• 2016

Dual energy computed tomography (DECT) is used to classify two materials and quantify the mass density of each material in the human body. An energy modulation filter based DECT could acquire two images, which are generated by the low- and high-energy photon spectra, in one scan, with one tube and detector. In the case of DECT using the energy modulation filter, the filter should perform the optimization process for the type of materials and thicknesses for generating two photon spectra. In this study, Geant4 Monte-Carlo simulation toolkit was used to execute the optimization process for determining the property of the energy modulation filter. In the process, various materials used for the energy modulation filter are copper (Cu, $8.96g/cm^3$), niobium (Nb, $8.57g/cm^3$), stannum (Sn, $7.31g/cm^3$), gold (Au, $19.32g/cm^3$), and lead (Pb, $11.34g/cm^3$). The thickness of the modulation filter varied from 0.1 mm to 1.0 mm. To evaluate the overlap region of the low- and high-energy spectrum, Geant4 Monte-Carlo simulation is used. The variation of the photon flux and the mean energy of photon spectrum that passes through the energy modulation filter are evaluated. In the primary photon spectrum of 80 kVp, the optimal modulation filter is a 0.1 mm lead filter that can acquire the same mean energy of 140 kVp photon spectrum. The lead filter of 0.1 mm based dual energy CBCT is required to increase the tube current 4.37 times than the original tube current owing to the 77.1% attenuation in the filter.

• 한국의학물리학회지:의학물리
• /
• 제23권4호
• /
• pp.303-308
• /
• 2012

뇌정위 방사선수술의 선량계산을 위해 Geant4 기반의 응용 프로그램을 개발 하였다. 선형가속기에서 발생하는 방사선의 스펙트럼을 입력하기 위하여 사전에 실행하여 구한 스펙트럼에 각 에너지별로 구한 가중치를 곱하여 확률밀도를 구하였다. 이를 누적밀도로 변환하여 입력하도록 하였다. 메신저 클래스를 이용하여 다양한 형태의 MLC 조사면을 설정할 수 있도록 하였다. 갠트리와 테이블의 회전을 모사하기 위하여 rotateX와 rotateY라는 회전행렬을 사용하였다. 월드좌표 속에서 갠트리와 테이블을 정의하여 각각 회전을 구현하였다. 실제 환자의 자료는 CT의 dicom 파일에서 픽셀 크기, 매트릭스 크기 등의 정보와 픽셀의 HU를 밀도로 변환한 파일을 생성한 다음 이 파일을 이용 환자의 모델링에 이용 하였다. 환자의 모델링은 팬텀월드 안에 픽셀의 크기에 해당하는 복셀을 정의하고 이 복셀에 픽셀의 밀도와 이 밀도에 해당하는 물질을 할당해주었다.

• Nuclear Engineering and Technology
• /
• 제55권11호
• /
• pp.4019-4025
• /
• 2023

Recently, a new monkey computational phantom, called Visible Monkey, was developed for non-ionizing radiation studies in animal research. In this study, we extended its applications to ionizing radiation studies by implementing the voxel model of the Visible Monkey into three general-purpose Monte Carlo (MC) codes: MCNP6, PHITS, and Geant4. The implementation work for MCNP and PHITS was conducted using the LATTICE, UNIVERSE, and FILL cards. The G4VNestedParameterisation class was used for Geant4. Then, organ dose coefficients (DCs) for idealized photon beams in the antero-posterior direction were calculated using the three codes and compared, showing excellent agreement (differences <3%). Additionally, organ DCs in other directions (postero-anterior, left-lateral, and right-lateral) were calculated and compared with those of the newborn and 1-year-old reference phantoms. Significant differences were observed (e.g., the stomach DC of the monkey was 5-fold greater than that of the 1-year-old phantom at 0.03 MeV) while the differences tended to decrease with increasing energy (mostly <20% at 10 MeV). The results of this study allows conducting MC simulations using the Visible Monkey to estimate organ-level doses, which should be valuable to support/improve monkey experiments involving ionizing radiation exposures.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2015년도 추계학술논문요약집
• /
• pp.489-490
• /
• 2015

• Journal of Astronomy and Space Sciences
• /
• 제31권1호
• /
• pp.25-31
• /
• 2014

There has been a rapid increase of the concern on the space radiation effect on pilots, crew and passengers at the commercial aircraft altitude (~ 10 km) recently. It is because domestic airline companies, Korean Air and Asiana Airlines have just begun operating the polar routes over the North Pole since 2006 and 2009 respectively. CARI-6 and CARI-6M are commonly used space radiation estimation programs which are provided officially by the U.S. federal aviation administration (FAA). In this paper, the route doses and the annual radiation doses for Korean pilots and cabin crew were estimated by using CARI-6M based on 2012 flight records. Also the modeling concept was developed for our own space radiation estimation program which is composed of GEANT4 and NRLMSIS00 models. The GEANT4 model is used to trace the incident particle transports in the atmosphere and the NRLMSIS00 model is used to get the background atmospheric densities of various neutral atoms at the aircraft altitude. Also presented are the results of simple integration tests of those models and the plan to include the space weather variations through the solar proton event (SPE) prediction model such as UMASEP and the galactic cosmic ray (GCR) prediction model such as Badhwar-O'Neill 2010.

• Nuclear Engineering and Technology
• /
• 제53권8호
• /
• pp.2767-2773
• /
• 2021

We used the GEANT4 Monte Carlo MC Toolkit to simulate carbon ion beams incident on water, tissue, and bone, taking into account nuclear fragmentation reactions. Upon increasing the energy of the primary beam, the position of the Bragg-Peak transfers to a location deeper inside the phantom. For different materials, the peak is located at a shallower depth along the beam direction and becomes sharper with increasing electron density NZ. Subsequently, the generated depth dose of the Bragg curve is then benchmarked with experimental data from GSI in Germany. The results exhibit a reasonable correlation with GSI experimental data with an accuracy of between 0.02 and 0.08 cm, thus establishing the basis to adopt MC in heavy-ion treatment planning. The Kolmogorov-Smirnov K-S test further ascertained from a statistical point of view that the simulation data matched the experimentally measured data very well. The two-dimensional isodose contours at the entrance were compared to those around the peak position and in the tail region beyond the peak, showing that bone produces more dose, in comparison to both water and tissue, due to secondary doses. In the water, the results show that the maximum energy deposited per fragment is mainly attributed to secondary carbon ions, followed by secondary boron and beryllium. Furthermore, the number of protons produced is the highest, thus making the maximum contribution to the total dose deposition in the tail region. Finally, the associated spectra of neutrons and photons were analyzed. The mean neutron energy value was found to be 16.29 MeV, and 1.03 MeV for the secondary gamma. However, the neutron dose was found to be negligible as compared to the total dose due to their longer range.

• Journal of Radiation Protection and Research
• /
• 제49권1호
• /
• pp.29-39
• /
• 2024

Background: The gamma emission tomography (GET) device has been reported a reliable technique to inspect partial defects within spent nuclear fuel (SNF) of pin-by-pin level. However, the existing GET devices have low accuracy owing to the high attenuation and scatter probability for SNF inspection condition. The purpose of this study is to design and optimize a Yonsei single-photon emission computed tomography version 2 (YSECT.v.2) for fast inspection of SNF in water storage by acquisition of high-quality tomographic images. Materials and Methods: Using Geant4 (Geant4 Collaboration) and DETECT-2000 (Glenn F. Knoll et al.) Monte Carlo simulation, the geometrical structure of the proposed device was determined and its performance was evaluated for the ¹³⁷Cs source in water. In a Geant4-based assessment, proposed device was compared with the International Atomic Energy Agency (IAEA)-authenticated device for the quality of tomographic images obtained for 12 fuel sources in a 14 × 14 Westinghouse-type fuel assembly. Results and Discussion: According to the results, the length, slit width, and septal width of the collimator were determined to be 65, 2.1, and 1.5 mm, respectively, and the material and length of the trapezoidal-shaped scintillator were determined to be gadolinium aluminum gallium garnet and 45 mm, respectively. Based on the results of performance comparison between the YSECT.v.2 and IAEA's device, the proposed device showed 200 times higher performance in gamma-detection sensitivity and similar source discrimination probability. Conclusion: In this study, we optimally designed the GET device for improving the SNF inspection accuracy and evaluated its performance. Our results show that the YSECT.v.2 device could be employed for SNF inspection.

• 한국방사선학회논문지
• /
• 제12권5호
• /
• pp.557-563
• /
• 2018

동시 합성 보정 효과는 검출기의 효율이 향상할 때 그리고 선원과 검출기 사이의 거리가 가까울수록 크게 나타나는 것으로 알려져 있다. 점 선원($^{60}Co$)을 사용하여 검출기 중심축 방향 및 방사상 방향에서 거리에 따른 변화를 주어 P/T 비를 구하여 동시합성 보정을 하였다. 따라서 본 연구에서는 중심축 및 방사상 방향에서 동시합성 보정한 값들을 혼합부피선원(450 mL CRM source)에 적용하여 P/T에 따른 전체 피크효율 변화를 Geant4과 비교하였다. 또한 검출기와 시료가 아주 밀착된 상태에서 맵핑법에서 구한 효율을 환경시료 중에서 해양 시료인 미역에 적용하여 P/T 비의 적합성을 평가하고자 한다. 500 keV 이상의 효율의 영향을 받는 에너지 영역에 1,836 keV로 보정한 효율을 적용한 결과 측정값과 보정값의 상대오차는 3.2 % peak 효율이 보정되어 잘 일치하였다. 450 mL CRM source처럼 부피가 커질수록 P/T 비는 ${\pm}5%$까지 감소하였다. 이것은 검출기로부터 선원이 멀어짐에 따라 방출된 감마선의 산란이 많아지기 때문이며, 이처럼 P/T 변화는 동시합성 보정 피크 효율에 영향을 줌을 확인하였다.